[Federal Register Volume 84, Number 88 (Tuesday, May 7, 2019)]
[Notices]
[Pages 19964-19977]
From the Federal Register Online via the Government Publishing Office [www.gpo.gov]
[FR Doc No: 2019-08982]
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NUCLEAR REGULATORY COMMISSION
[NRC-2019-0112]
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.
[[Page 19965]]
This biweekly notice includes all notices of amendments issued, or
proposed to be issued, from April 9, 2019, to April 22, 2019. The last
biweekly notice was published on April 23, 2019.
DATES: Comments must be filed by June 6, 2019. A request for a hearing
must be filed by July 8, 2019.
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-2019-0112. Address
questions about NRC docket IDs in Regulations.gov to Jennifer Borges;
telephone: 301-287-9127; email: [email protected]. For technical
questions, contact the individual listed in the FOR FURTHER INFORMATION
CONTACT section of this document.
Mail comments to: Office of Administration, Mail Stop:
TWFN-7-A60M, U.S. Nuclear Regulatory Commission, Washington, DC 20555-
0001, ATTN: Program Management, Announcements and Editing Staff.
For additional direction on obtaining information and submitting
comments, see ``Obtaining Information and Submitting Comments'' in the
SUPPLEMENTARY INFORMATION section of this document.
FOR FURTHER INFORMATION CONTACT: Janet Burkhardt, Office of Nuclear
Reactor Regulation, U.S. Nuclear Regulatory Commission, Washington, DC
20555-0001; telephone: 301-415-1384; email: [email protected].
SUPPLEMENTARY INFORMATION:
I. Obtaining Information and Submitting Comments
A. Obtaining Information
Please refer to Docket ID NRC-2019-0112, facility name, unit
number(s), plant docket number, application date, and subject when
contacting the NRC about the availability of information for this
action. You may obtain publicly-available information related to this
action by any of the following methods:
Federal Rulemaking Website: Go to http://www.regulations.gov and search for Docket ID NRC-2019-0112.
NRC's Agencywide Documents Access and Management System
(ADAMS): You may obtain publicly-available documents online in the
ADAMS Public Documents collection at http://www.nrc.gov/reading-rm/adams.html. To begin the search, select ``Begin Web-based ADAMS
Search.'' For problems with ADAMS, please contact the NRC's Public
Document Room (PDR) reference staff at 1-800-397-4209, 301-415-4737, or
by email to [email protected]. The ADAMS accession number for each
document referenced (if it is available in ADAMS) is provided the first
time that it is mentioned in this document.
NRC's PDR: You may examine and purchase copies of public
documents at the NRC's PDR, Room O1-F21, One White Flint North, 11555
Rockville Pike, Rockville, Maryland 20852.
B. Submitting Comments
Please include Docket ID NRC-2019-0112, facility name, unit
number(s), plant docket number, application date, and subject in your
comment submission.
The NRC cautions you not to include identifying or contact
information that you do not want to be publicly disclosed in your
comment submission. The NRC will post all comment submissions at http://www.regulations.gov as well as enter the comment submissions into
ADAMS. The NRC does not routinely edit comment submissions to remove
identifying or contact information.
If you are requesting or aggregating comments from other persons
for submission to the NRC, then you should inform those persons not to
include identifying or contact information that they do not want to be
publicly disclosed in their comment submission. Your request should
state that the NRC does not routinely edit comment submissions to
remove such information before making the comment submissions available
to the public or entering the comment into ADAMS.
II. Background
Pursuant to Section 189a.(2) of the Atomic Energy Act of 1954, as
amended (the Act), the U.S. Nuclear Regulatory Commission (NRC) is
publishing this regular biweekly notice. The Act requires the
Commission to publish notice of any amendments issued, or proposed to
be issued, and grants the Commission the authority to issue and make
immediately effective any amendment to an operating license or combined
license, as applicable, upon a determination by the Commission that
such amendment involves no significant hazards consideration,
notwithstanding the pendency before the Commission of a request for a
hearing from any person.
III. Notice of Consideration of Issuance of Amendments to Facility
Operating Licenses and Combined Licenses and Proposed No Significant
Hazards Consideration Determination
The Commission has made a proposed determination that the following
amendment requests involve no significant hazards consideration. Under
the Commission's regulations in Sec. 50.92 of title 10 of the Code of
Federal Regulations (10 CFR), this means that operation of the facility
in accordance with the proposed amendment would not (1) involve a
significant increase in the probability or consequences of an accident
previously evaluated; or (2) create the possibility of a new or
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
[[Page 19966]]
action. Petitions shall be filed in accordance with the Commission's
``Agency Rules of Practice and Procedure'' in 10 CFR part 2. Interested
persons should consult a current copy of 10 CFR 2.309. The NRC's
regulations are accessible electronically from the NRC Library on the
NRC's website at http://www.nrc.gov/reading-rm/doc-collections/cfr/.
Alternatively, a copy of the regulations is available at the NRC's
Public Document Room, located at One White Flint North, Room O1-F21,
11555 Rockville Pike (First Floor), Rockville, Maryland 20852. If a
petition is filed, the Commission or a presiding officer will rule on
the petition and, if appropriate, a notice of a hearing will be issued.
As required by 10 CFR 2.309(d) the petition should specifically
explain the reasons why intervention should be permitted with
particular reference to the following general requirements for
standing: (1) The name, address, and telephone number of the
petitioner; (2) the nature of the petitioner's right under the Act to
be made a party to the proceeding; (3) the nature and extent of the
petitioner's property, financial, or other interest in the proceeding;
and (4) the possible effect of any decision or order which may be
entered in the proceeding on the petitioner's interest.
In accordance with 10 CFR 2.309(f), the petition must also set
forth the specific contentions which the petitioner seeks to have
litigated in the proceeding. Each contention must consist of a specific
statement of the issue of law or fact to be raised or controverted. In
addition, the petitioner must provide a brief explanation of the bases
for the contention and a concise statement of the alleged facts or
expert opinion which support the contention and on which the petitioner
intends to rely in proving the contention at the hearing. The
petitioner must also provide references to the specific sources and
documents on which the petitioner intends to rely to support its
position on the issue. The petition must include sufficient information
to show that a genuine dispute exists with the applicant or licensee on
a material issue of law or fact. Contentions must be limited to matters
within the scope of the proceeding. The contention must be one which,
if proven, would entitle the petitioner to relief. A petitioner who
fails to satisfy the requirements at 10 CFR 2.309(f) with respect to at
least one contention will not be permitted to participate as a party.
Those permitted to intervene become parties to the proceeding,
subject to any limitations in the order granting leave to intervene.
Parties have the opportunity to participate fully in the conduct of the
hearing with respect to resolution of that party's admitted
contentions, including the opportunity to present evidence, consistent
with the NRC's regulations, policies, and procedures.
Petitions must be filed no later than 60 days from the date of
publication of this notice. Petitions and motions for leave to file new
or amended contentions that are filed after the deadline will not be
entertained absent a determination by the presiding officer that the
filing demonstrates good cause by satisfying the three factors in 10
CFR 2.309(c)(1)(i) through (iii). The petition must be filed in
accordance with the filing instructions in the ``Electronic Submissions
(E-Filing)'' section of this document.
If a hearing is requested, and the Commission has not made a final
determination on the issue of no significant hazards consideration, the
Commission will make a final determination on the issue of no
significant hazards consideration. The final determination will serve
to establish when the hearing is held. If the final determination is
that the amendment request involves no significant hazards
consideration, the Commission may issue the amendment and make it
immediately effective, notwithstanding the request for a hearing. Any
hearing would take place after issuance of the amendment. If the final
determination is that the amendment request involves a significant
hazards consideration, then any hearing held would take place before
the issuance of the amendment unless the Commission finds an imminent
danger to the health or safety of the public, in which case it will
issue an appropriate order or rule under 10 CFR part 2.
A State, local governmental body, Federally-recognized Indian
Tribe, or agency thereof, may submit a petition to the Commission to
participate as a party under 10 CFR 2.309(h)(1). The petition should
state the nature and extent of the petitioner's interest in the
proceeding. The petition should be submitted to the Commission no later
than 60 days from the date of publication of this notice. The petition
must be filed in accordance with the filing instructions in the
``Electronic Submissions (E-Filing)'' section of this document, and
should meet the requirements for petitions set forth in this section,
except that under 10 CFR 2.309(h)(2) a State, local governmental body,
or Federally-recognized Indian Tribe, or agency thereof does not need
to address the standing requirements in 10 CFR 2.309(d) if the facility
is located within its boundaries. Alternatively, a State, local
governmental body, Federally-recognized Indian Tribe, or agency thereof
may participate as a non-party under 10 CFR 2.315(c).
If a hearing is granted, any person who is not a party to the
proceeding and is not affiliated with or represented by a party may, at
the discretion of the presiding officer, be permitted to make a limited
appearance pursuant to the provisions of 10 CFR 2.315(a). A person
making a limited appearance may make an oral or written statement of
his or her position on the issues but may not otherwise participate in
the proceeding. A limited appearance may be made at any session of the
hearing or at any 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
[[Page 19967]]
submitting a petition or other adjudicatory document (even in instances
in which the participant, or its counsel or representative, already
holds an NRC-issued digital ID certificate). Based upon this
information, the Secretary will establish an electronic docket for the
hearing in this proceeding if the Secretary has not already established
an electronic docket.
Information about applying for a digital ID certificate is
available on the NRC's public website at http://www.nrc.gov/site-help/e-submittals/getting-started.html. Once a participant has obtained a
digital ID certificate and a docket has been created, the participant
can then submit adjudicatory documents. Submissions must be in Portable
Document Format (PDF). Additional guidance on PDF submissions is
available on the NRC's public website at http://www.nrc.gov/site-help/electronic-sub-ref-mat.html. A filing is considered complete at the
time the document is submitted through the NRC's E-Filing system. To be
timely, an electronic filing must be submitted to the E-Filing system
no later than 11:59 p.m. Eastern Time on the due date. Upon receipt of
a transmission, the E-Filing system time-stamps the document and sends
the submitter an email notice confirming receipt of the document. The
E-Filing system also distributes an email notice that provides access
to the document to the NRC's Office of the General Counsel and any
others who have advised the Office of the Secretary that they wish to
participate in the proceeding, so that the filer need not serve the
document on those participants separately. Therefore, applicants and
other participants (or their counsel or representative) must apply for
and receive a digital ID certificate before adjudicatory documents are
filed so that they can obtain access to the documents via the E-Filing
system.
A person filing electronically using the NRC's adjudicatory E-
Filing system may seek assistance by contacting the NRC's Electronic
Filing Help Desk through the ``Contact Us'' link located on the NRC's
public website at http://www.nrc.gov/site-help/e-submittals.html, by
email to [email protected], or by a toll-free call at 1-866-672-
7640. The NRC Electronic Filing Help Desk is available between 9 a.m.
and 6 p.m., Eastern Time, Monday through Friday, excluding government
holidays.
Participants who believe that they have a good cause for not
submitting documents electronically must file an exemption request, in
accordance with 10 CFR 2.302(g), with their initial paper filing
stating why there is good cause for not filing electronically and
requesting authorization to continue to submit documents in paper
format. Such filings must be submitted by: (1) First class mail
addressed to the Office of the Secretary of the Commission, U.S.
Nuclear Regulatory Commission, Washington, DC 20555-0001, Attention:
Rulemaking and Adjudications Staff; or (2) courier, express mail, or
expedited delivery service to the Office of the Secretary, 11555
Rockville Pike, Rockville, Maryland 20852, Attention: Rulemaking and
Adjudications Staff. Participants filing adjudicatory documents in this
manner are responsible for serving the document on all other
participants. Filing is considered complete by first-class mail as of
the time of deposit in the mail, or by courier, express mail, or
expedited delivery service upon depositing the document with the
provider of the service. A presiding officer, having granted an
exemption request from using E-Filing, may require a participant or
party to use E-Filing if the presiding officer subsequently determines
that the reason for granting the exemption from use of E-Filing no
longer exists.
Documents submitted in adjudicatory proceedings will appear in the
NRC's electronic hearing docket which is available to the public at
https://adams.nrc.gov/ehd, unless excluded pursuant to an order of the
Commission or the presiding officer. If you do not have an NRC-issued
digital ID certificate as described above, click cancel when the link
requests certificates and you will be automatically directed to the
NRC's electronic hearing dockets where you will be able to access any
publicly available documents in a particular hearing docket.
Participants are requested not to include personal privacy information,
such as social security numbers, home addresses, or personal phone
numbers in their filings, unless an NRC regulation or other law
requires submission of such information. For example, in some
instances, individuals provide home addresses in order to demonstrate
proximity to a facility or site. With respect to copyrighted works,
except for limited excerpts that serve the purpose of the adjudicatory
filings and would constitute a Fair Use application, participants are
requested not to include copyrighted materials in their submission.
For further details with respect to these license amendment
applications, see the application for amendment which is available for
public inspection in ADAMS and at the NRC's PDR. For additional
direction on accessing information related to this document, see the
``Obtaining Information and Submitting Comments'' section of this
document.
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: February 27, 2019. A publicly-available
version is in ADAMS under Accession No. ML19058A768.
Description of amendment request: The proposed amendments would
modify Technical Specification (TS) 5.5.12 to allow extension of the
Type A and Type C test intervals. The extension is based on the
adoption of the Nuclear Energy Institute (NEI) topical report NEI 94-
01, ``Industry Guideline for Implementing Performance-Based Option of
10 CFR part 50, Appendix J,'' Revision 3-A, dated July 2012, and
conditions and limitations set forth in NEI 94-01, Revision 2-A, dated
October 2008. The proposed amendments would also make administrative
changes to TS 5.5.12.
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 activity involves the revision of the Brunswick
Steam Electric Plant (BSEP) Units 1 and 2 Technical Specification
(TS) 5.5.12, Primary Containment Leakage Rate Testing Program, to
allow the extension of the Type A integrated leakage rate test
(ILRT) containment test interval to 15 years, and the extension of
the Type C test interval to 75 months. Per the guidance provided in
Nuclear Energy Institute (NEI) 94-01, Industry Guideline for
Implementing Performance-Based Option of 10 CFR 50, Appendix J,
Revision 3-A, the current Type A test interval of 120 months (i.e.,
10 years) would be extended on a permanent basis to no longer than
15 years from the last Type A test. The current Type C test interval
of 60 months for selected components would be extended on a
performance basis to no longer than 75 months. Extensions of up to
nine months for Types A, B and C tests are permissible only for non-
routine emergent conditions.
The proposed interval extensions do not involve either a
physical change to the plant or a change in the manner in which the
plant is operated or controlled. The containment is designed to
provide an essentially leak tight barrier against the uncontrolled
release of radioactivity to the environment for postulated
accidents. As such, the
[[Page 19968]]
containment and the testing requirements invoked to periodically
demonstrate the integrity of the containment exist to ensure the
plant's ability to mitigate the consequences of an accident, and do
not involve the prevention or identification of any precursors of an
accident.
The change in Type A test frequency to once-per-fifteen-years,
measured as an increase to the total integrated plant risk for those
accident sequences influenced by Type A testing, based on the
probabilistic risk assessment (PRA) is 4.98E-03 person-rem/year for
Unit 1 and 4.67E-03 person-rem/year for Unit 2. Electric Power
Research Institute (EPRI) Report No. 1009325, Revision 2-A states
that a very small population dose is defined as an increase of less
than 1.0 person-rem per year or less than 1 percent of the total
population dose, whichever is less restrictive for the risk impact
assessment of the extended ILRT intervals. This is consistent with
the Nuclear Regulatory Commission (NRC) Final Safety Evaluation for
NEI 94-01 and EPRI Report No. 1009325, Revision 2A. Moreover, the
risk impact when compared to other severe accident risks is
negligible. Therefore, the proposed extension does not involve a
significant increase in the probability of an accident previously
evaluated.
In addition, as documented in NUREG-1493, ``Performance-Based
Containment Leak-Test Program,'' dated September 1995, Types B and C
tests have identified a very large percentage of containment leakage
paths, and the percentage of containment leakage paths that are
detected only by Type A testing is very small. The BSEP Unit 1 and
Unit 2 Type A test history supports this conclusion.
The integrity of the containment is subject to two types of
failure mechanisms that can be categorized as: (1) Activity based,
and (2) time based. Activity based failure mechanisms are defined as
degradation due to system and/or component modifications or
maintenance. Local leak rate test requirements and administrative
controls such as configuration management and procedural
requirements for system restoration ensure that containment
integrity is not degraded by plant modifications or maintenance
activities. The design and construction requirements of the
containment combined with the containment inspections performed in
accordance with American Society of Mechanical Engineers (ASME)
Boiler and Pressure Vessel (B&PV) Code, Section XI, Rules for
Inservice Inspection of Nuclear Power Plant Components, Containment
Maintenance Rule Inspections, Containment Coatings Program and TS
requirements serve to provide a high degree of assurance that the
containment would not degrade in a manner that is detectable only by
a Type A test (ILRT). Based on the above, the proposed test interval
extensions do not significantly increase the consequences of an
accident previously evaluated.
The proposed amendment also proposes administrative changes to
the exceptions in Units 1 and 2 TS 5.5.12.c and f. TS exception
5.5.12.c reference[s] NEI 94-01 Revision 0 and TS exception 5.5.12.f
reference[s] ANSI/ANS [American National Standards Institute/
American Nuclear Society] 56.8-1994. This change proposes to update
the referenced documents in these two TS exceptions to reflect the
adoption of NEI 94-01, Revision 3-A and ANSI/ANS 56.8-2002,
accordingly. This administrative change does not impact any
accidents previously evaluated.
Therefore, the proposed changes do not result in 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 amendment to the BSEP Units 1 and 2 TS 5.5.12,
``Primary Containment Leakage Rate Testing Program,'' involves the
extension of the BSEP, Units 1 and 2 Type A containment test
interval to 15 years and the extension of the Type C test interval
to 75 months. The containment and the testing requirements to
periodically demonstrate the integrity of the containment exist to
ensure the plant's ability to mitigate the consequences of an
accident.
The proposed change does not involve a physical modification to
the plant (i.e., no new or different type of equipment will be
installed) nor does it alter the design, configuration, or change
the manner in which the plant is operated or controlled beyond the
standard functional capabilities of the equipment.
The proposed amendment also proposes administrative changes to
the exceptions in Units 1 and 2 TS 5.5.12.c and f. TS exception
5.5.12.c reference[s] NEI 94-01 Revision 0 and TS exception 5.5.12.f
reference[s] ANSI/ANS 56.8-1994. This change proposes to update the
referenced documents in these two TS exceptions to reflect the
adoption of NEI 94-01, Revision 3-A and ANSI/ANS 56.8-2002,
accordingly. This administrative change to the references listed in
TS 5.5.12.c and f, does not create the possibility of a new or
different kind of accident from any accident previously evaluated.
Therefore, the proposed change does not create the possibility
of a new or different kind of accident from any previously
evaluated.
3. Does the proposed change involve a significant reduction in a
margin of safety?
Response: No.
The proposed amendment to Unit 1 and Unit 2 TS 5.5.12 involves
the extension of the BSEP Type A containment test interval to 15
years and the extension of the Type C to 75 months. This amendment
does not alter the manner in which safety limits, limiting safety
system set points, or limiting conditions for operation are
determined. The specific requirements and conditions of the TS
Containment Leak Rate Testing Program exist to ensure that the
degree of containment structural integrity and leak-tightness that
is considered in the plant safety analysis is maintained. The
overall containment leak rate limit specified by TS is maintained.
The proposed change involves the extension of the interval
between Type A containment leak rate tests and Type C tests for
BSEP, Units 1 and 2. The proposed surveillance interval extension is
bounded by the 15-year ILRT interval and the 75-month Type C test
interval currently authorized within NEI 94-01, Revision 3-A.
Industry experience supports the conclusion that Type B and C
testing detects a large percentage of containment leakage paths and
that the percentage of containment leakage paths that are detected
only by Type A testing is small. The containment inspections
performed in accordance with Option B to 10 CFR 50, Appendix J and
the overlapping inspection activities performed as part of ASME
Section Xl, and the TS serve to provide a high degree of assurance
that the containment would not degrade in a manner that is
detectable only by Type A testing. The combination of these factors
ensures that the margin of safety in the plant safety analysis is
maintained. The design, operation, testing methods and acceptance
criteria for Types A, B, and C containment leakage tests specified
in applicable codes and standards would continue to be met, with the
acceptance of this proposed change, since these are not affected by
changes to the Type A and Type C test intervals.
The proposed amendment also proposes administrative changes to
the exceptions in Units 1 and 2 TS 5.5.12. Two exceptions listed in
the Units 1 and 2 TS 5.5.12 contain references to revisions and
years of the ANSI/ANS 56.8 and NEI 94-01. Units 1 and 2 TS 5.5.12
exception c references NEI 94-01, Revision 0 and Units 1 and 2 TS
5.5.12 exception f references ANSI/ANS 56.8-1994. This change
proposes to update the referenced documents in these two TS
exceptions to reflect the adoption of NEI 94-01, Revision 3-A and
ANSI/ANS 56.8-2002, accordingly. This administrative change does not
change how the unit is operated or maintained, thus there is no
reduction in any margins of safety.
Therefore, the proposed changes do not involve a significant
reduction in a margin of safety.
The NRC staff has reviewed the licensee's analysis and, based on
this review, it appears that the three standards of 10 CFR 50.92(c) are
satisfied. Therefore, the NRC staff proposes to determine that the
amendment request involves no significant hazards consideration.
Attorney for licensee: Kathryn B. Nolan, Deputy General Counsel,
550 South Tryon Street, M/C DEC45A, Charlotte, NC 28202.
NRC Branch Chief: Undine Shoop.
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: March 4, 2019. A publicly-available
version is in ADAMS under Accession No. ML19063B740.
Description of amendment request: The proposed amendments would
modify Technical Specification Surveillance Requirements (SRs) 3.4.3.2
[[Page 19969]]
and 3.5.1.11 by replacing the current requirement to verify the safety
relief valves (SRVs) open when manually actuated with an alternate
requirement that verifies the SRVs are capable of being opened.
Additionally, the proposed change would revise the frequency for
performing these SRs to be in accordance with the Inservice Testing
(IST) Program.
Basis for proposed no significant hazards consideration
determination: As required by 10 CFR 50.91(a), the licensee has
provided its analysis of the issue of no significant hazards
consideration, which is presented below:
1. Does the proposed 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 SR 3.4.3.2 and SR 3.5.1.11
by replacing the current requirement to verify the SRVs open when
manually actuated with an alternate requirement that verifies the
SRVs are capable of being opened through a series of overlapping
tests and requires the testing to be completed on a frequency in
accordance with the IST Program. The proposed SR testing will
continue to demonstrate proper SRV operation without the need for
in-situ testing with reactor steam. This testing fully meets the
requirements of the American Society of Mechanical Engineers (ASME)
Code for Operation and Maintenance of Nuclear Power Plants (OM Code)
for safety and relief valves. Performing testing in accordance with
the IST Program retains appropriate legal control over the testing
methodology and specified frequency, since performance is required
and is governed by a code adopted into the regulation, i.e., 10 CFR
50.55a. 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
event. 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 amendment 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 revises SR 3.4.3.2 and SR 3.5.1.11 by
replacing the current requirement to verify the SRVs open when
manually actuated with an alternate requirement that verifies the
SRVs are capable of being opened through a series of overlapping
tests and updating the frequency to be in accordance with the IST
Program. 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 amendment does not create the
possibility of a new or different kind of accident from any accident
previously evaluated.
3. Does the proposed change involve a significant reduction in a
margin of safety?
Response: No.
The proposed change revises SR 3.4.3.2 and SR 3.5.1.11 by
replacing the current requirement to verify the SRVs open when
manually actuated with an alternate requirement that verifies the
SRVs are capable of being opened through a series of overlapping
tests and updating the frequency to be in accordance with the IST
Program. The proposed SR testing will continue to demonstrate proper
SRV operation without the need for in-situ testing with reactor
steam. 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) will continue to be met.
Therefore, the proposed amendment does 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.
Entergy Nuclear Operations, Inc., Docket No. 50-255, Palisades Nuclear
Plant (PNP), Van Buren County, Michigan
Date of amendment request: March 8, 2019. A publicly available
version is in ADAMS under Accession No. ML19067A004.
Description of amendment request: The proposed amendment would
revise the full compliance date for the fire protection program
transition license condition to allow an extension for the
implementation of the remaining modifications necessary to achieve full
compliance with 10 CFR 50.48(c).
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 to the PNP [renewed facility operating
license] RFOL to change the full compliance date for the fire
protection program transition license condition to allow additional
time for the implementation of the remaining modifications necessary
to achieve full compliance with 10 CFR 50.48(c) is administrative in
nature. This change does not alter accident analysis assumptions,
add any initiators, or affect the function of plant systems or the
manner in which systems are operated, maintained, modified, tested,
or inspected. The proposed change does not require any plant
modifications which affect the performance capability of the
structures, systems, and components relied upon to mitigate the
consequences of postulated accidents, and has no impact on the
probability or consequences of an accident previously evaluated.
Therefore, this 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 to the PNP RFOL [Renewed Facility Operating
License] to change the full compliance date for the fire protection
program transition license condition to allow additional time for
the implementation of the remaining modifications necessary to
achieve full compliance with 10 CFR 50.48(c) is administrative in
nature. This proposed change does not alter accident analysis
assumptions, add any initiators, or affect the function of plant
systems or the manner in which systems are operated, maintained,
modified, tested, or inspected. The proposed change does not require
any plant modifications which affect the performance capability of
the structures, systems, and components relied upon to mitigate the
consequences of postulated accidents and does not create the
possibility of a new or different kind of accident from any accident
previously evaluated.
Therefore, this change does not create the possibility of a new
or different kind of accident from an accident previously evaluated.
3. Does the proposed change involve a significant reduction in a
margin of safety?
Response: No.
The proposed change to the PNP RFOL to change the full
compliance implementation date for the fire protection program
transition license condition to allow additional time for
implementation of the remaining modifications necessary to achieve
full compliance with 10 CFR 50.48(c) is administrative in nature.
Plant safety margins
[[Page 19970]]
are established through limiting conditions for operation, limiting
safety system settings, and safety limits specified in the technical
specifications. Because there is no change to established safety
margins as a result of this change, the proposed change does not
involve a significant reduction in a margin of safety.
Therefore, this change does not involve a significant reduction
in a margin of safety.
The NRC staff has reviewed the licensee's analysis and, based on
this review, it appears that the three standards of 10 CFR 50.92(c) are
satisfied. Therefore, the NRC staff proposes to determine that the
amendment request involves no significant hazards consideration.
Attorney for licensee: Anna V. Jones, Senior Counsel, Entergy
Services, Inc., 101 Constitution Avenue NW, Suite 200 East, Washington,
DC 20001.
NRC Branch Chief: David J. Wrona.
Exelon Generation Company, LLC, Docket Nos. STN 50-456 and STN 50-457,
Braidwood Station, Units 1 and 2, Will County, Illinois and Docket Nos.
STN 50-454 and STN 50-455, Byron Station, Unit Nos. 1 and 2, Ogle
County, Illinois
Date of amendment request: December 13, 2018, as supplemented by
letter dated February 14, 2019. Publicly-available versions are in
ADAMS under Accession Nos. ML18352B063 and ML19050A399, respectively.
Description of amendment request: The proposed amendment would
revise the technical specifications to permit the use of risk-informed
completion times in accordance with Technical Specification Task Force
(TSTF)-505, Revision 2, ``Provide Risk-Informed Extended Completion
Times--RITSTF Initiative 4b,'' which is Attachment 3 to TSTF letter
dated July 2, 2018 (ADAMS Accession No. ML18183A493).
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 changes permit the extension of Completion Times
provided the associated risk is assessed and managed in accordance
with the NRC approved Risk-Informed Completion Time Program. The
proposed changes do not involve a significant increase in the
probability of an accident previously evaluated because the changes
involve no change to the plant or its modes of operation. The
proposed changes do not increase the consequences of an accident
because the design-basis mitigation function of the affected systems
is not changed and the consequences of an accident during the
extended Completion Time are no different from those during the
existing Completion Time.
Therefore, the proposed 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 changes do not change the design, configuration, or
method of operation of the plant. The proposed changes do not
involve a physical alteration of the plant (no new or different kind
of equipment will be installed).
Therefore, the proposed changes do not create the possibility of
a new or different kind of accident from any accident previously
evaluated.
3. Does the proposed change involve a significant reduction in a
margin of safety?
Response: No.
The proposed changes permit the extension of Completion Times
provided that risk is assessed and managed in accordance with the
NRC approved Risk-Informed Completion Time Program. The proposed
changes implement a risk-informed configuration management program
to assure that adequate margins of safety are maintained.
Application of these new specifications and the configuration
management program considers cumulative effects of multiple systems
or components being out of service and does so more effectively than
the current TS.
Therefore, the proposed changes do not involve a significant
reduction in a margin of safety.
The NRC staff has reviewed the licensee's analysis and, based on
this review, it appears that the three standards of 10 CFR 50.92(c) are
satisfied. Therefore, the NRC staff proposes to determine that the
requested amendments involve no significant hazards consideration.
Attorney for licensee: Tamra Domeyer, Associate General Counsel,
Exelon Generation Company, LLC, 4300 Winfield Road, Warrenville, IL
60555.
NRC Branch Chief: David J. Wrona.
Exelon Generation Company, LLC, Docket Nos. STN 50-456 and STN 50-457,
Braidwood Station, Units 1 and 2, Will County, Illinois and Docket Nos.
STN 50-454 and STN 50-455, Byron Station, Unit Nos. 1 and 2, Ogle
County, Illinois
Date of amendment request: January 31, 2019. A publicly-available
version is in ADAMS under Accession No. ML19032A149.
Description of amendment request: The proposed amendment would
revise technical specifications (TS) for inoperable snubbers by adding
Limiting Condition for Operation (LCO) 3.0.9. The change is consistent
with the NRC-approved Technical Specification Task Force (TSTF)
Standard Technical Specifications Change Traveler, TSTF-372, ``Addition
of LCO 3.0.8, lnoperability of Snubbers.'' The availability of this TS
improvement was announced in the Federal Register on May 4, 2005 (70 FR
23252). Because Braidwood Station, Units 1 and 2, and Byron Station,
Unit Nos. 1 and 2, already have a TS identified as LCO 3.0.8, adoption
of TSTF-372 will be identified as LCO 3.0.9.
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 allows a delay time before declaring
supported Technical Specifications (TS) systems inoperable when the
associated snubber(s) cannot perform its required safety function.
Entrance into Actions or delaying entrance into Actions is not an
initiator of any accident previously evaluated. Consequently, the
probability of an accident previously evaluated is not significantly
increased. The consequences of an accident while relying on the
delay time allowed before declaring a TS supported system inoperable
and taking its Conditions and Required Actions are no different than
the consequences of an accident under the same plant conditions
while relying on the existing TS supported system Conditions and
Required Actions. Therefore, the consequences of an accident
previously evaluated are not significantly increased by this change.
Therefore, this 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 allows a delay time before declaring
supported TS systems inoperable when the associated snubber(s)
cannot perform its required safety function. The proposed change
does not involve a physical alteration of the plant (no new or
different type of equipment will be installed) or a change in the
methods governing normal plant operation.
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?
[[Page 19971]]
Response: No.
The proposed change allows a delay time before declaring
supported TS systems inoperable when the associated snubber(s)
cannot perform its required safety function. The proposed change
restores an allowance in the pre-Improved Standard Technical
Specifications (ISTS) conversion TS that was unintentionally
eliminated by the conversion. The pre-ISTS TS were considered to
provide an adequate margin of safety for plant operation, as does
the post-ISTS conversion TS.
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
requested amendments involve no significant hazards consideration.
Attorney for licensee: Tamra Domeyer, Associate General Counsel,
Exelon Generation Company, LLC, 4300 Winfield Road, Warrenville, IL
60555.
NRC Branch Chief: David J. Wrona.
Florida Power and Light Company, Docket No. 50-250 and 50-251, Turkey
Point Nuclear Generating Unit Nos. 3 and 4, Miami-Dade County, Florida
Date of amendment request: February 14, 2019. A publicly-available
version is in ADAMS under Accession No. ML19045A617.
Description of amendment request: The amendments would revise the
Technical Specifications (TS) related to certain equipment shared
between the two units when one unit is shut down. Additionally, the
amendments remove an inappropriate footnote that allows an exception
from TS 4.0.4.
Basis for proposed no significant hazards consideration
determination: As required by 10 CFR 50.91(a), the licensee has
provided its analysis of the issue of no significant hazards
consideration, which is presented below:
1. Does the proposed amendment involve a significant increase in
the probability or consequences of an accident previously evaluated?
Response: No.
The technical specification requirements associated with the
proposed change to the TS are not initiators of any accidents
previously evaluated, so the probability of accidents previously
evaluated is unaffected by the proposed change. The proposed change
does not alter the design, function, or operation of any plant
structure, system, or component (SSC). The capability of any
operable TS-required SSC to perform its specified safety function is
not impacted by the proposed change. As a result, the outcomes of
accidents previously evaluated are unaffected. Therefore, the
proposed change does not result in 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 challenge the integrity or
performance of any safety-related systems. No plant equipment is
installed or removed, and the change does not alter the design,
physical configuration, or method of operation of any plant SSC. No
physical changes are made to the plant, so no new causal mechanisms
are introduced. Therefore, the proposed change to the TS does not
create the possibility of a new or different kind of accident from
any accident previously evaluated. 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 ability of any operable SSC to perform its designated safety
function is unaffected by the proposed change. The proposed change
does not alter any safety analyses assumptions, safety limits,
limiting safety system settings, or method of operating the plant.
The change does not adversely affect plant operating margins or the
reliability of equipment credited in the safety analyses. 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: Debbie Hendell, Managing Attorney--Nuclear,
Florida Power & Light Company, 700 Universe Blvd. MS LAW/JB, Juno
Beach, FL 33408-0420.
NRC Branch Chief: Undine Shoop.
Omaha Public Power District (OPPD) Docket No. 50-285, Fort Calhoun
Station, Unit No. 1 (FCS), Fort Calhoun, Nebraska
Date of amendment request: February 28, 2019. A publicly-available
version is in ADAMS under Accession No. ML19064A758.
Description of amendment request: The proposed amendment would
replace the FCS Permanently Defueled Emergency Plan and associated
Emergency Action Level (EAL) technical bases document with the
Independent Spent Fuel Storage Installation Only Emergency Plan (IOEP)
and its associated Independent Spent Fuel Storage Installation (ISFSI)
EAL Technical Bases Document. The IOEP will be used at FCS during the
period when all spent fuel is stored in the FCS ISFSI. This proposed
change reflects the complete removal of all fuel from the spent fuel
pool (SFP) and permits specific reductions in the size and makeup of
the Emergency Response Organization due to the elimination of the
remaining design basis accident related to spent fuel handling. OPPD
expects that all spent fuel will be completely transferred to the ISFSI
by the middle of 2020.
Basis for proposed no significant hazards consideration
determination: As required by 10 CFR 50.91(a), the licensee has
provided its analysis of the issue of no significant hazards
consideration, which is presented below:
1. Does the proposed amendment involve a significant increase in
the probability or consequences of an accident previously evaluated?
Response: No.
The proposed amendment would modify the FCS facility operating
license by revising the emergency plan and EAL scheme. FCS has
permanently ceased power operations and is permanently defueled. The
proposed amendment is conditioned on all spent nuclear fuel being
removed from wet storage in the SFP and placed in dry storage within
the ISFSI. Occurrence of postulated accidents associated with spent
fuel stored in a SFP is no longer credible in a SFP devoid of such
fuel. The proposed amendment has no effect on plant systems,
structures, or components (SSC) and no effect on the capability of
any plant SSC to perform its design function. The proposed amendment
would not increase the likelihood of the malfunction of any plant
SSC. The proposed amendment would have no effect on any of the
previously evaluated accidents in the FCS [Defueled Safety Analysis
Report] DSAR.
Because FCS has permanently ceased power operations, the
generation of fission products has ceased and the remaining source
term continues to decay. This continues to significantly reduce the
consequences of previously evaluated postulated accidents.
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 amendment constitutes a revision of the emergency
planning function commensurate with the ongoing and anticipated
reduction in radiological source term at FCS.
The proposed amendment does not involve a physical alteration of
the plant. No new or different types of equipment will be installed
and there are no physical modifications to existing equipment as a
result of the
[[Page 19972]]
proposed amendment. Similarly, the proposed amendment would not
physically change any SSC involved in the mitigation of any
postulated accidents. Thus, no new initiators or precursors of a new
or different kind of accident are created. Furthermore, the proposed
amendment does not create the possibility of a new failure mode
associated with any equipment or personnel failures. The credible
events for the ISFSI remain unchanged.
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.
Because the 10 CFR part 50 license for FCS no longer authorizes
operation of the reactor or emplacement or retention of fuel into
the reactor vessel, as specified in 10 CFR 50.82(a)(2), the
occurrence of postulated accidents associated with reactor operation
is no longer credible. With all spent nuclear fuel transferred out
of wet storage from the SFP and placed in dry storage within the
ISFSI, a fuel handling accident is no longer credible. There are no
credible events that would result in radiological releases beyond
the site boundary exceeding the EPA PAG exposure levels, as detailed
in the EPA's PAG Manual ``Protective Action Guides and Planning
Guidance for Radiological Incidents'' dated January 2017 (EPA PAG
Manual).
The proposed amendment does not involve a change in the plant's
design, configuration, or operation. The proposed amendment does not
affect either the way in which the plant SSCs perform their safety
function or their design margins. Because there is no change to the
physical design of the plant, there is no change to these margins.
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: Stephen M. Bruckner, Attorney, Fraser
Stryker PC LLO, 500 Energy Plaza, 409 South 17th Street, Omaha, NE
68102.
NRC Branch Chief: Bruce A. Watson.
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: February 14, 2019. A publicly-available
version is in ADAMS under Accession No. ML19045A698.
Description of amendment request: The proposed amendments would
revise the intake structure physical security classification in the
DCPP Security Plan and Emergency Plan.
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 changes to the Diablo Canyon Power [Nuclear] Plant
(DCPP) emergency action levels (EALs) do not physically impact the
plant structures, systems, or components (SSCs) or the manner in
which SSCs perform their design function. The proposed changes
neither adversely affect accident initiators or precursors, nor
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. A concurrent accident with a hostile action
is not assumed to occur.
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 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
or removed) or a change in the method of plant operation. The
proposed changes will not introduce failure modes that could result
in a new accident, and the change[s] [do] not alter assumptions made
in the safety analysis. The proposed changes to the DCPP EALs are
not initiators of any accidents.
Therefore, the proposed change does not create the possibility
of a new or different 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 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 changes do not impact operation of the plant or its
response to transients or accidents. The proposed changes do not
affect the Technical Specifications or the Operating Licenses. The
proposed changes do not involve a change in the method of plant
operation, and no accident analyses will be affected by the proposed
changes. Additionally, the proposed changes will not relax any
criteria used to establish safety limits and will not relax any
safety system settings. The safety analysis acceptance criteria are
not affected by these changes. The proposed changes will not result
in plant operation in a configuration outside the design basis. The
proposed changes do not adversely affect systems that respond to
safely shut down the plant and to maintain the plant in a safe
shutdown condition. The Emergency Plan will continue to activate an
emergency response commensurate with the extent of degradation of
plant 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 requests involve no significant hazards consideration.
Attorney for licensee: Jennifer Post, Esq., Pacific Gas and
Electric Company, P.O. Box 7442, San Francisco, CA 94120.
NRC Branch Chief: Robert J. Pascarelli.
Southern Nuclear Operating Company, Docket Nos. 52-025 and 52-026,
Vogtle Electric Generating Plant Units 3 and 4, Burke County, Georgia
Date of amendment request: March 25, 2019. A publicly-available
version is in ADAMS under Accession No. ML19084A309.
Description of amendment request: The requested amendment proposes
to change the Technical Specifications (TS) (Combined License Appendix
A), as well as plant-specific Tier 2 information. Specifically, the
requested amendment proposes to change TS Sections 1.0, 3.1, 3.2, 3.3,
3.9, and 5.5. The Surveillance Requirements (SRs) requiring manual
Channel Checks, Channel Operational Tests, Actuation Logic Tests and
Actuation Logic Output Tests to be performed on Protection and Safety
Monitoring System (PMS) components are proposed to be removed from the
TSs. The approach for satisfying the reactor trip and engineered safety
feature actuation system response time test SRs for the PMS racks is
proposed to be changed.
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.
[[Page 19973]]
The proposed changes do not affect the safety limits as
described in the plant-specific TS. In addition, the limiting safety
system settings and limiting control settings continue to be met
with the proposed changes to the plant-specific TS SRs. The proposed
changes do not adversely affect the operation of any systems or
equipment that initiate an analyzed accident or alter any
structures, systems, and components (SSCs) accident initiator or
initiating sequence of events.
The proposed changes do not result in any increase in
probability of an analyzed accident occurring and maintain the
initial conditions and operating limits required by the accident
analysis, and the analyses of normal operation and anticipated
operational occurrences, so that the consequences of postulated
accidents are not changed.
Therefore, the requested 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 changes do not affect the safety limits as
described in the plant- specific TS. In addition, the limiting
safety system settings and limiting control settings continue to be
met with the proposed changes to the plant-specific TS limiting
conditions for operation, applicability, actions, and SRs. The
proposed changes do not affect the operation of any systems or
equipment that may initiate a new or different kind of accident or
alter any SSC such that a new accident initiator or initiating
sequence of events is created.
These proposed changes do not adversely affect any other SSC
design functions or methods of operation in a manner that results in
a new failure mode, malfunction, or sequence of events that affect
safety-related or nonsafety-related equipment. Therefore, this
activity does not allow for a new fission product release path,
result in a new fission product barrier failure mode, or create a
new sequence of events that results in significant fuel cladding
failures.
Therefore, the requested amendment does not create the
possibility of a new or different kind of accident from any accident
previously evaluated.
3. Does the proposed amendment involve a significant reduction
in a margin of safety?
Response: No.
The proposed changes do not affect the safety limits as
described in the plant- specific TS. In addition, the limiting
safety system settings and limiting control settings continue to be
met with the proposed changes to the plant-specific TS limiting
conditions for operation, applicability, actions, and SRs. The
proposed changes do not affect the initial conditions and operating
limits required by the accident analysis, and the analyses of normal
operation and anticipated operational occurrences, so that the
acceptance limits specified in the Updated Final Safety Analysis
Report (UFSAR) are not exceeded. The proposed changes satisfy the
same safety functions in accordance with the same requirements as
stated in the UFSAR. These changes do not adversely affect any
design code, function, design analysis, safety analysis input or
result, or design/safety margin.
No safety analysis or design basis acceptance limit/criterion is
challenged or exceeded by the proposed changes, and no margin of
safety is reduced.
Therefore, the requested 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. Dixon-Herrity.
Susquehanna Nuclear, LLC, Docket Nos. 50-387 and 50-388, Susquehanna
Steam Electric Station, Units 1 and 2, Luzerne County, Pennsylvania
Date of amendment request: March 28, 2019. A publicly-available
version is in ADAMS under Accession No. ML19087A208.
Description of amendment request: The amendments would eliminate
the second Completion Times from certain Technical Specifications
(TSs). The second Completion Times limit the time allowed from
discovery of failure to meet a limiting condition for operation (LCO)
until the LCO is met. The proposed changes are consistent with
previously NRC-approved Technical Specifications Task Force (TSTF)
Traveler TSTF-439, Revision 2, ``Eliminate Second Completion Times
Limiting Time from Discovery of Failure to Meet an LCO.''
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 change involve a significant increase in
the probability or consequences of an accident previously evaluated?
Response: No.
The proposed change eliminates second Completion Times from the
TS. Completion Times are not an initiator to any accident previously
evaluated. As a result, the probability of an accident previously
evaluated is not affected. The consequences of an accident during
the revised Completion Time are no different than the consequences
of the same accident during the existing Completion Times. As a
result, the consequences of an accident previously evaluated are not
affected by this change. The proposed change does not alter or
prevent the ability of structures, systems, or components from
performing their intended function to mitigate the consequences of
an initiating event within the assumed acceptance limits. 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 evaluated.
Further, the proposed change does not increase the types or amounts
of radioactive effluent that may be released offsite nor significant
increase [in] individual or cumulative occupational/public radiation
exposures. The proposed change is consistent with the safety
analysis assumptions and resultant consequences.
Therefore, the proposed change does not involve a significant
increase in the probability or consequences of an accident
previously evaluated.
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 involve a physical alteration of
the plant (i.e., no new or different type of equipment will be
installed) or a change in the methods governing normal plant
operation. The proposed change does not alter any 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 change involve a significant reduction in a
margin of safety?
Response: No.
The proposed change to delete the second Completion Times does
not alter the manner in which safety limits, limiting safety system
settings, or LCOs are determined. The safety analysis acceptance
criteria are not affected by this change. The proposed change will
not result in plant operation in a configuration outside of the
design basis.
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: Damon D. Obie, Associate General Counsel,
Talen Energy Supply, LLC, 835 Hamilton St., Suite 150, Allentown, PA
18101.
NRC Branch Chief: James G. Danna.
[[Page 19974]]
Tennessee Valley Authority, Docket Nos. 50-259, 50-260, and 50-296,
Browns Ferry Nuclear Plant, Units 1, 2, and 3, Limestone County,
Alabama
Date of amendment request: January 25, 2019. A publicly-available
version is in ADAMS under Accession No. ML19031C826.
Description of amendment request: The amendments would replace
existing technical specification (TS) requirements related to
operations with a potential for draining the reactor vessel (OPDRV)
with new requirements on reactor pressure vessel (RPV) water inventory
control (WIC) to continue 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.
Basis for proposed no significant hazards consideration
determination: As required by 10 CFR 50.91(a), the licensee has
provided its analysis of the issue of no significant hazards
consideration, which is presented below:
1. Does the proposed amendment involve a significant increase in
the probability or consequences of an accident previously evaluated?
Response: No.
The proposed change replaces existing TS requirements related to
OPDRVs with new requirements on RPV WIC that will protect Safety
Limit 2.1.1.3. Draining of RPV water inventory in Mode 4 (i.e., cold
shutdown) and Mode 5 (i.e., refueling) is not an accident previously
evaluated and, therefore, replacing the existing TS controls to
prevent or mitigate such an event with a new set of controls has no
effect on any accident previously evaluated. RPV water inventory
control in Mode 4 or Mode 5 is not an initiator of any accident
previously evaluated. The existing OPDRV controls or the proposed
RPV WIC controls are not mitigating actions assumed in any accident
previously evaluated.
The proposed change reduces the probability of an unexpected
draining event (which is not a previously evaluated accident) by
imposing new requirements on the limiting time in which an
unexpected draining event could result in the reactor vessel water
level dropping to the top of the active fuel (TAF). These controls
require cognizance of the plant configuration and control of
configurations with unacceptably short drain times.
These requirements reduce the probability of an unexpected
draining event. The current TS requirements are only mitigating
actions and impose no requirements that reduce the probability of an
unexpected draining event.
The proposed change reduces the consequences of an unexpected
draining event (which is not a previously evaluated accident) by
requiring an Emergency Core Cooling System (ECCS) subsystem to be
operable at all times in Modes 4 and 5. The current TS requirements
do not require any water injection systems, ECCS or otherwise, to be
Operable in certain conditions in Mode 5. The change in requirement
from two ECCS subsystems to one ECCS subsystem in Modes 4 and 5 does
not significantly affect the consequences of an unexpected draining
event because the proposed Required Actions ensure equipment is
available within the limiting drain time that is as capable of
mitigating the event as the current requirements. The proposed
controls provide escalating compensatory measures to be established
as calculated drain times decrease, such as verification of a second
method of water injection and additional confirmations that
containment and/or filtration would be available if needed.
The proposed change reduces or eliminates some requirements that
were determined to be unnecessary to manage the consequences of an
unexpected draining event, such as automatic initiation of an ECCS
subsystem and control room ventilation. These changes do not affect
the consequences of any accident previously evaluated because a
draining event in Modes 4 and 5 is not a previously evaluated
accident and the requirements are not needed to adequately respond
to a draining event.
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 change replaces existing TS requirements related to
OPDRVs with new requirements on RPV WIC that will protect Safety
Limit 2.1.1.3. The proposed change will not alter the design
function of the equipment involved. Under the proposed change, some
systems that are currently required to be operable during OPDRVs
would be required to be available within the limiting drain time or
to be in service depending on the limiting drain time. Should those
systems be unable to be placed into service, the consequences are no
different than if those systems were unable to perform their
function under the current TS requirements.
The event of concern under the current requirements and the
proposed change is an unexpected draining event. The proposed change
does not create new failure mechanisms, malfunctions, or accident
initiators that would cause a draining event or a new or different
kind of accident not previously evaluated or included in the design
and licensing bases.
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 proposed change replaces existing TS requirements related to
OPDRVs with new requirements on RPV WIC. The current requirements do
not have a stated safety basis and no margin of safety is
established in the licensing basis. The safety basis for the new
requirements is to protect Safety Limit 2.1.1.3. New requirements
are added to determine the limiting time in which the RPV water
inventory could drain to the top of the fuel in the reactor vessel
should an unexpected draining event occur. Plant configurations that
could result in lowering the RPV water level to the TAF within one
hour are now prohibited. New escalating compensatory measures based
on the limiting drain time replace the current controls. The
proposed TS establish a safety margin by providing defense-in-depth
to ensure that the Safety Limit is protected and to protect the
public health and safety. While some less restrictive requirements
are proposed for plant configurations with long calculated drain
times, the overall effect of the change is to improve plant safety
and to add safety margin.
Therefore, the proposed change does not involve a significant
reduction in a margin of safety.
The NRC staff has reviewed the licensee's analysis and, based on
this review, it appears that the three standards of 10 CFR 50.92(c) are
satisfied. Therefore, the NRC staff proposes to determine that the
amendment request involves no significant hazards consideration.
Attorney for licensee: General Counsel, Tennessee Valley Authority,
400 West Summit Hill Drive, 6A West Tower, Knoxville, TN 37902.
NRC Branch Chief: Undine Shoop.
Wolf Creek Nuclear Operating Corporation, Docket No. 50-482, Wolf Creek
Generating Station, Unit 1, Coffey County, Kansas
Date of amendment request: February 25, 2019. A publicly-available
version is in ADAMS under Accession No. ML19064A591.
Description of amendment request: The amendment would revise
Technical Specification (TS) 3.6.3, ``Containment Isolation Valves,''
to remove use of a blind flange to meet Limiting Condition for
Operation (LCO) 3.6.3, Required Action D.1. In addition, a change to
Surveillance Requirement (SR) 3.6.3.1 is proposed to remove use of a
blind flange.
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 changes to TS LCO 3.6.3 and SR 3.6.3.1 have no
effect on the requirement for systems to be OPERABLE and have no
effect on the application of TS actions. Since the proposed change
does not significantly
[[Page 19975]]
affect system OPERABILITY the proposed change will have no
significant effect on the initiating events for accidents previously
evaluated and will have no significant effect on the ability of the
systems to mitigate accidents previously evaluated.
Therefore, it is concluded that this change does not involve a
significant increase in the probability or consequences of an
accident previously evaluated.
2. Does the proposed change create the possibility of a new or
different kind of accident from any accident previously evaluated?
Response: No.
The proposed change to update the TS does not affect the design
or function of any plant systems. The proposed change does not
change the Operability requirements for plant systems or the actions
taken when plant systems are not OPERABLE.
Therefore, it is concluded that this change does not create the
possibility of a new or different kind of accident from any accident
previously evaluated.
3. Does the proposed change involve a significant reduction in a
margin of safety?
Response: No.
The proposed change updates TS LCO 3.6.3, Required Action D.1 to
remove use of a blind flange. It does not result in changes in plant
operation. The proposed change to SR 3.6.3.1 removes the use of a
blind flange. As a result, plant safety is either improved or
unaffected.
Therefore, it is concluded that this change does not involve a
significant reduction in a margin of safety.
The NRC staff has reviewed the licensee's analysis and, based on
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: Jay Silberg, Esq., Pillsbury Winthrop Shaw
Pittman LLP, 1200 17th Street NW, Washington, DC 20036.
NRC Branch Chief: Robert J. Pascarelli.
IV. Notice of Issuance of Amendments to Facility Operating Licenses and
Combined Licenses
During the period since publication of the last biweekly notice,
the Commission has issued the following amendments. The Commission has
determined for each of these amendments that the application complies
with the standards and requirements of the Atomic Energy Act of 1954,
as amended (the Act), and the Commission's rules and regulations. The
Commission has made appropriate findings as required by the Act and the
Commission's rules and regulations in 10 CFR chapter I, which are set
forth in the license amendment.
A notice of consideration of issuance of amendment to facility
operating license or combined license, as applicable, proposed no
significant hazards consideration determination, and opportunity for a
hearing in connection with these actions, was published in the Federal
Register as indicated.
Unless otherwise indicated, the Commission has determined that
these amendments satisfy the criteria for categorical exclusion in
accordance with 10 CFR 51.22. Therefore, pursuant to 10 CFR 51.22(b),
no environmental impact statement or environmental assessment need be
prepared for these amendments. If the Commission has prepared an
environmental assessment under the special circumstances provision in
10 CFR 51.22(b) and has made a determination based on that assessment,
it is so indicated.
For further details with respect to the action see (1) the
applications for amendment, (2) the amendment, and (3) the Commission's
related letter, Safety Evaluation and/or Environmental Assessment as
indicated. All of these items can be accessed as described in the
``Obtaining Information and Submitting Comments'' section of this
document.
Duke Energy Carolinas, LLC, Docket Nos. 50-413 and 50-414, Catawba
Nuclear Station, Units 1 and 2 (Catawba), York County, South Carolina
Duke Energy Carolinas, LLC, Docket Nos. 50-369 and 50-370, McGuire
Nuclear Station, Units 1 and 2 (McGuire), Mecklenburg County, North
Carolina
Duke Energy Progress, Inc., Docket No. 50-400; Shearon Harris Nuclear
Power Plant, Unit 1 (Harris), Wake County, North Carolina
Duke Energy Progress, Inc., Docket No. 50-261, H. B. Robinson Steam
Electric Plant, Unit No. 2 (Robinson), Darlington County, South
Carolina
Date of amendment request: May 10, 2018.
Brief description of amendments: The amendments modified the
Technical Specifications (TSs) for Catawba, McGuire, Harris, and
Robinson. Specifically, ventilation system heaters will be removed from
Catawba TSs 3.6.10, ``Annulus Ventilation System (AVS)''; 3.7.10,
``Control Room Area Ventilation System (CRAVS)''; 3.7.12, ``Auxiliary
Building Filtered Ventilation Exhaust System (ABFVES)''; 3.7.13, ``Fuel
Handling Ventilation Exhaust System (FHVES)''; 3.9.3, ``Containment
Penetrations''; 5.5.11, ``Ventilation Filter Testing Program (VFTP)'';
and 5.6.6, ``Ventilation Systems Heater Report''; and McGuire TSs
3.6.10, ``Annulus Ventilation System (AVS)''; 3.7.9, ``Control Room
Area Ventilation System (CRAVS)''; 5.5.11, ``Ventilation Filter Testing
Program (VFTP)''; and 5.6.6, ``Ventilation Systems Heater Failure
Report.'' The specified relative humidity for charcoal testing in the
ventilation system Surveillance Requirement (for Harris) and
Ventilation Filter Testing Program (for Robinson) is revised from 70
percent to 95 percent and the ventilation system heaters will be
removed from the Harris TSs \3/4\.7.6, ``Control Room Emergency
Filtration System''; \3/4\.7.7, ``Reactor Auxiliary Building (RAB)
Emergency Exhaust System''; and \3/4\.9.12, ``Fuel Handling Building
Emergency Exhaust System''; and Robinson TSs 3.7.11, ``Fuel Building
Air Cleanup System (FBACS),'' and 5.5.11, ``Ventilation Filter Testing
Program (VFTP).'' The proposed changes are consistent with Technical
Specifications Task Force (TSTF) Traveler TSTF-522, ``Revise
Ventilation System Surveillance Requirements to Operate for 10 Hours
per Month,'' Revision 0. Additionally, an administrative error is being
corrected in McGuire's TS 5.5.11, ``Ventilation Filter Testing Program
(VFTP).''
Date of issuance: April 18, 2019.
Effective date: As of the date of issuance and shall be implemented
within 120 days of issuance.
Amendment Nos: 301/297 (Catawba), 313/292 (McGuire), 170 (Harris),
and 262 (Robinson). A publicly-available version is in ADAMS under
Accession No. ML19050A297; documents related to these amendments are
listed in the Safety Evaluation enclosed with the amendments.
Facility Operating License Nos. NPF-35 and NPF-52 (Catawba), NPF-63
(Harris), NPF-9 and NPF-17 (McGuire), and DPR-23 (Robinson): The
amendments revised the Facility Operating Licenses and Technical
Specifications.
Date of initial notice in Federal Register: October 23, 2018 (83 FR
53511).
The Commission's related evaluation of the amendment is contained
in a Safety Evaluation dated April 18, 2019.
No significant hazards consideration comments received: No.
Exelon Generation Company, LLC, Docket Nos. 50-317 and 50-318, Calvert
Cliffs Nuclear Power Plant, Units 1 and 2, Calvert County, Maryland
Date of amendment request: April 20, 2018.
Brief description of amendments: The amendments revised the Calvert
Cliffs Nuclear Power Plant, Units 1 and 2, Technical Specifications to
remove an
[[Page 19976]]
exception to the minimum education requirements for shift technical
advisors. Specifically, Technical Specification Section 5.2.2.g.3
related to specific requirements for shift technical advisor personnel
education and training has been deleted.
Date of issuance: April 19, 2019.
Effective date: As of the date of issuance and shall be implemented
within 60 days of issuance.
Amendment Nos.: 329 (Unit 1); 307 (Unit 2). A publicly-available
version is in ADAMS under Accession No. ML19053A588; documents related
to these amendments are listed in the Safety Evaluation enclosed with
the amendments.
Renewed Facility Operating License Nos. DPR-53 and DPR-69: The
amendments revised the Renewed Facility Operating License and Technical
Specifications.
Date of initial notice in Federal Register: July 3, 2018 (83 FR
31183).
The Commission's related evaluation of the amendments is contained
in a Safety Evaluation dated April 19, 2019.
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: March 19, 2018, as supplemented by
letters dated August 13, 2018, and November 20, 2018.
Brief description of amendment: The amendment revised the on-shift
staffing and the emergency response organization in the site emergency
plan for the post-shutdown and permanently defueled condition.
Date of issuance: April 18, 2019.
Effective date: Upon the licensee's submittal of the certifications
required by 10 CFR 50.82(a)(1)(i) and (ii) and shall be implemented
within 90 days of the effective date of the amendment, but may not
exceed December 31, 2019.
Amendment No.: 296. A publicly-available version is in ADAMS under
Accession No. ML19065A114; documents related to this amendment are
listed in the Safety Evaluation enclosed with the amendment.
Renewed Facility Operating License No. DPR-50: The amendment
revised the emergency plan.
Date of initial notice in Federal Register: July 17, 2018 (83 FR
33268). The supplemental letters dated August 13, 2018, and November
20, 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 April 18, 2019.
No significant hazards consideration comments received: No.
Indiana Michigan Power Company, Docket Nos. 50-315 and 50-316, Donald
C. Cook Nuclear Plant (CNP), Unit Nos. 1 and 2, Berrien County,
Michigan
Date of amendment request: May 4, 2018.
Brief description of amendments: The amendments revised the CNP,
Units 1 and 2, technical specification (TS) usage rules for completion
times, limiting conditions for operation (LCOs), and surveillance
requirements (SRs) based on Technical Specification Task Force (TSTF)
Traveler TSTF-529, ``Clarify Use and Application Rules,'' Revision 4.
Specifically, the licensee proposed changes to TS Section 1.3,
``Completion Time,'' and LCO 3.0.4 and SR 3.0.3 in TS Section 3.0,
``Limiting Condition for Operation (LCO) Applicability.''
Date of issuance: April 10, 2019.
Effective date: As of the date of issuance and shall be implemented
within 60 days of issuance.
Amendment Nos.: 344 (Unit 1) and 326 (Unit 2). A publicly-available
version is in ADAMS under Accession No. ML19031B966; documents related
to these amendments are listed in the Safety Evaluation enclosed with
the amendments.
Facility Operating License Nos. DPR-58 and DPR-74: The amendments
revised the Renewed Facility Operating Licenses and Technical
Specifications.
Date of initial notice in Federal Register: July 17, 2018 (83 FR
33269).
The Commission's related evaluation of the amendment is contained
in a Safety Evaluation dated April 10, 2019.
No significant hazards consideration comments received: No.
Northern States Power Company--Minnesota (NSPM), Docket No. 50-263,
Monticello Nuclear Generating Plant, Wright County, Minnesota
Date of amendment request: November 12, 2018.
Brief description of amendment: The amendment revised the safety
limit minimum critical power ratio for two recirculation loop and
single recirculation loop operation. The amendment also revised
Technical Specifications 2.1.1 and 5.6.3 to remove outdated and
duplicate information.
Date of issuance: April 22, 2019.
Effective date: As of the date of issuance and shall be implemented
prior to the startup from the spring 2019 refueling outage.
Amendment No.: 201. A publicly-available version is in ADAMS under
Accession No. ML19074A269; documents related to this amendment are
listed in the Safety Evaluation enclosed with the amendment.
Renewed Facility Operating License No. DPR-22. The amendment
revised the Renewed Facility Operating License and Technical
Specifications.
Date of initial notice in Federal Register: February 5, 2019 (84 FR
1803).
The Commission's related evaluation of the amendment is contained
in a Safety Evaluation dated April 22, 2019.
No significant hazards consideration comments received: No.
Northern States Power Company--Minnesota, Docket Nos. 50-282 and 50-
306, Prairie Island Nuclear Generating Plant, Units 1 and 2, Goodhue
County, Minnesota
Date of amendment request: March 15, 2018, as supplemented by
letter dated September 17, 2018.
Brief description of amendment: The amendments revised the
technical specifications to adopt Technical Specifications Task Force
(TSTF) Standard Technical Specifications (STS) Change Traveler TSTF-
425, Revision 3, ``Relocate Surveillance Frequencies to Licensee
Control-RITSTF [Risk-Informed TSTF] Initiative 5b,'' requiring future
surveillance frequency changes to be made in accordance with NEI 04-10,
an approved methodology.
Date of issuance: April 16, 2019.
Effective date: As of the date of issuance and shall be implemented
within 120 days of issuance.
Amendment Nos.: 226--Unit 1; 214--Unit 2. A publicly-available
version is in ADAMS under Accession No. ML19045A480; documents related
to these amendments are listed in the Safety Evaluation enclosed with
the amendments.
Renewed Facility Operating License Nos. DPR-42 and DPR-60: The
amendments revised the Renewed Facility Operating Licenses and
Technical Specifications.
Date of initial notice in Federal Register: May 22, 2018 (83 FR
23735). The supplemental letter dated September 17, 2018, provided
additional information that clarified the application, did not expand
the scope of the application as originally noticed, and did not change
the staff's original proposed no significant hazards consideration
determination as published in the Federal Register.
[[Page 19977]]
The Commission's related evaluation of the amendment is contained
in a Safety Evaluation dated April 16, 2019.
No significant hazards consideration comments received: No.
PSEG Nuclear LLC and Exelon Generation Company, LLC, Docket Nos. 50-272
and 50-311, Salem Nuclear Generating Station, Unit Nos. 1 and 2, Salem
County, New Jersey
Date of amendment request: June 29, 2018.
Brief description of amendments: The amendments deleted duplicative
technical specification (TS) requirements for the refueling water
storage tank in TS 3.1.2.6, ``Borated Water Sources--Operating,'' and
revised TS 3.5.5, ``Refueling Water Storage Tank,'' to ensure
compliance with assumptions used in the design-basis accident and
containment response analyses and to make Salem Nuclear Generating
Station, Unit Nos. 1 and 2, TS requirements for the refueling water
storage tank, consistent with NUREG-1431, Revision 4, ``Standard
Technical Specifications--Westinghouse Plants.''
Date of issuance: April 11, 2019.
Effective date: As of the date of issuance and shall be implemented
within 60 days from the date of issuance.
Amendment Nos.: 328 (Unit No. 1) and 309 (Unit No. 2). A publicly-
available version is in ADAMS under Accession No. ML19077A336;
documents related to these amendments are listed in the Safety
Evaluation enclosed with the amendments.
Renewed Facility Operating License Nos. DPR-70 and DPR-75: The
amendments revised the Renewed Facility Operating Licenses and
Technical Specifications.
Date of initial notice in Federal Register: August 28, 2018 (83 FR
43907).
The Commission's related evaluation of the amendments is contained
in a Safety Evaluation dated April 11, 2019.
No significant hazards consideration comments received: No.
South Carolina Electric & Gas Company, South Carolina Public Service
Authority, Docket No. 50-395, Virgil C. Summer Nuclear Station, Unit
No. 1, Fairfield County, South Carolina
Date of amendment request: December 12, 2018.
Brief description of amendment: The amendment removed an expired
one-time extension to Technical Specification (TS) Surveillance
Requirement 4.3.3.6 and removes the Index from the TSs, placing it
under licensee control. These changes are administrative and non-
technical.
Date of issuance: April 10, 2019.
Effective date: As of the date of issuance and shall be implemented
within 90 days of issuance.
Amendment No.: 214. A publicly-available version is in ADAMS under
Accession No. ML19074A222, documents related to this amendment are
listed in the Safety Evaluation enclosed with the amendment.
Renewed Facility Operating License No. NPF-12: Amendment revised
the Renewed Facility Operating License and the Technical
Specifications.
Date of initial notice in Federal Register: January 30, 2019 (84 FR
495).
The Commission's related evaluation of the amendment is contained
in a Safety Evaluation dated April 10, 2019.
No significant hazards consideration comments received: No.
Union Electric Company, Docket No. 50-483, Callaway Plant, Unit 1
(Callaway), Callaway County, Missouri
Date of amendment request: March 9, 2018, as supplemented by
letters dated January 23, February 8, and March 7, 2019.
Brief description of amendment: The amendment added new Technical
Specification (TS) 3.7.20, ``Class 1E Electrical Equipment Air
Conditioning (A/C) System,'' to the Callaway TSs. New TS 3.7.20
includes (1) a Limiting Condition for Operation (LCO) statement, (2) an
Applicability statement, during which the LCO must be met, (3) ACTIONS
to be applied when the LCO is not met, including Conditions, Required
Actions, and Completion Times, and (4) Surveillance Requirements with a
specified Frequency to demonstrate that the LCO is met for the Class 1E
Electrical Equipment A/C System trains at Callaway. The change enhanced
the capability of one Class 1E electrical equipment A/C train to
provide adequate area cooling for both trains of Class 1E electrical
equipment during normal and accident conditions.
Date of issuance: April 18, 2019.
Effective date: As of the date of issuance and shall be implemented
within 120 days from the date of issuance.
Amendment No.: 219. A publicly-available version is in ADAMS under
Accession No. ML19073A001; documents related to this amendment are
listed in the Safety Evaluation enclosed with the amendment.
Renewed Facility Operating License No. NPF-30: The amendment
revised the Renewed Facility Operating License and Technical
Specifications.
Date of initial notice in Federal Register: July 3, 2018 (83 FR
31194). The supplements dated January 23, February 8, and March 7,
2019, provided additional information that clarified the application,
did not expand the scope of the application as originally noticed, and
did not change the NRC staff's original proposed no significant hazards
consideration determination as published in the Federal Register.
The Commission's related evaluation of the amendment is contained
in a Safety Evaluation dated April 18, 2019.
No significant hazards consideration comments received: No.
Dated at Rockville, Maryland, this 29th day of April 2019.
For the Nuclear Regulatory Commission.
Kathryn M. Brock,
Deputy Director, Division of Operating Reactor Licensing, Office of
Nuclear Reactor Regulation.
[FR Doc. 2019-08982 Filed 5-6-19; 8:45 am]
BILLING CODE 7590-01-P