[Federal Register Volume 82, Number 156 (Tuesday, August 15, 2017)]
[Notices]
[Pages 38714-38722]
From the Federal Register Online via the Government Publishing Office [www.gpo.gov]
[FR Doc No: 2017-16998]
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NUCLEAR REGULATORY COMMISSION
[NRC-2017-0175]
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 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.
This biweekly notice includes all notices of amendments issued, or
proposed to be issued, from July 18 to July 31, 2017. The last biweekly
notice was published on August 1, 2017.
DATES: Comments must be filed by September 14, 2017. A request for a
hearing must be filed by October 16, 2017.
ADDRESSES: You may submit comments by any of the following methods:
Federal Rulemaking Web site: Go to http://www.regulations.gov and search for Docket ID NRC-2017-0175. Address
questions about NRC dockets to Carol Gallagher; telephone: 301-415-
3463; email: [email protected]. For technical questions, contact
the individual listed in the FOR FURTHER INFORMATION CONTACT section of
this document.
Mail comments to: Cindy Bladey, Office of Administration,
Mail Stop: TWFN-8-D36M, U.S. Nuclear Regulatory Commission, Washington,
DC 20555-0001.
For additional direction on obtaining information and submitting
comments, see ``Obtaining Information and Submitting Comments'' in the
SUPPLEMENTARY INFORMATION section of this document.
FOR FURTHER INFORMATION CONTACT: Beverly Clayton, Office of Nuclear
Reactor Regulation, U.S. Nuclear Regulatory Commission, Washington, DC
20555-0001; telephone: 301-415-3475, email: [email protected].
SUPPLEMENTARY INFORMATION:
I. Obtaining Information and Submitting Comments
A. Obtaining Information
Please refer to Docket ID NRC-2017-0175, 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 Web site: Go to http://www.regulations.gov and search for Docket ID NRC-2017-0175.
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 ``ADAMS Public Documents'' and
then 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-2017-0175, 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 posts all comment submissions at http://www.regulations.gov as well as entering 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 submissions into ADAMS.
II. 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.
[[Page 38715]]
The Commission expects that the need to take this action will occur
very infrequently.
A. Opportunity To Request a Hearing and Petition for Leave To Intervene
Within 60 days after the date of publication of this notice, any
persons (petitioner) whose interest may be affected by this action may
file a request for a hearing and petition for leave to intervene
(petition) with respect to the action. Petitions shall be filed in
accordance with the Commission's ``Agency Rules of Practice and
Procedure'' in 10 CFR part 2. Interested persons should consult a
current copy of 10 CFR 2.309. The NRC's regulations are accessible
electronically from the NRC Library on the NRC's Web site 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's Web site 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
[[Page 38716]]
days prior to the filing deadline, the participant should contact the
Office of the Secretary by email at [email protected], or by
telephone at 301-415-1677, to (1) request a digital identification (ID)
certificate, which allows the participant (or its counsel or
representative) to digitally sign submissions and access the E-Filing
system for any proceeding in which it is participating; and (2) advise
the Secretary that the participant will be submitting a petition or
other adjudicatory document (even in instances in which the
participant, or its counsel or representative, already holds an NRC-
issued digital ID certificate). Based upon this information, the
Secretary will establish an electronic docket for the hearing in this
proceeding if the Secretary has not already established an electronic
docket.
Information about applying for a digital ID certificate is
available on the NRC's public Web site 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 Web site 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 Web site at http://www.nrc.gov/site-help/e-submittals.html, by
email to [email protected], or by a toll-free call at 1-866-672-
7640. The NRC Electronic Filing Help Desk is available between 9 a.m.
and 6 p.m., Eastern Time, Monday through Friday, excluding government
holidays.
Participants who believe that they have a good cause for not
submitting documents electronically must file an exemption request, in
accordance with 10 CFR 2.302(g), with their initial paper filing
stating why there is good cause for not filing electronically and
requesting authorization to continue to submit documents in paper
format. Such filings must be submitted by: (1) First class mail
addressed to the Office of the Secretary of the Commission, U.S.
Nuclear Regulatory Commission, Washington, DC 20555-0001, Attention:
Rulemaking and Adjudications Staff; or (2) courier, express mail, or
expedited delivery service to the Office of the Secretary, 11555
Rockville Pike, Rockville, Maryland, 20852, Attention: Rulemaking and
Adjudications Staff. Participants filing adjudicatory documents in this
manner are responsible for serving the document on all other
participants. Filing is considered complete by first-class mail as of
the time of deposit in the mail, or by courier, express mail, or
expedited delivery service upon depositing the document with the
provider of the service. A presiding officer, having granted an
exemption request from using E-Filing, may require a participant or
party to use E-Filing if the presiding officer subsequently determines
that the reason for granting the exemption from use of E-Filing no
longer exists.
Documents submitted in adjudicatory proceedings will appear in the
NRC's electronic hearing docket which is available to the public at
https://adams.nrc.gov/ehd, unless excluded pursuant to an order of the
Commission or the presiding officer. If you do not have an NRC-issued
digital ID certificate as described above, click cancel when the link
requests certificates and you will be automatically directed to the
NRC's electronic hearing dockets where you will be able to access any
publicly available documents in a particular hearing docket.
Participants are requested not to include personal privacy information,
such as social security numbers, home addresses, or personal phone
numbers in their filings, unless an NRC regulation or other law
requires submission of such information. For example, in some
instances, individuals provide home addresses in order to demonstrate
proximity to a facility or site. With respect to copyrighted works,
except for limited excerpts that serve the purpose of the adjudicatory
filings and would constitute a Fair Use application, participants are
requested not to include copyrighted materials in their submission.
For further details with respect to these license amendment
applications, see the application for amendment which is available for
public inspection in ADAMS and at the NRC's PDR. For additional
direction on accessing information related to this document, see the
``Obtaining Information and Submitting Comments'' section of this
document.
Arizona Public Service Company, et al., Docket Nos. STN 50-528, STN 50-
529, and STN 50-530, Palo Verde Nuclear Generating Station, Units 1, 2,
and 3 (PVNGS), Maricopa County, Arizona
Date of amendment request: June 22, 2017. A publicly-available
version is in ADAMS under Accession No. ML17173A877.
Description of amendment request: The amendment would revise the
PVNGS Technical Specifications (TSs) to eliminate TS Section 5.5.8,
``Inservice Testing Program.'' A new defined term, ``Inservice Testing
Program,'' will be added to the TS definitions section. This request is
consistent with Technical Specification Task Force (TSTF) Traveler
TSTF-545, Revision 3, ``TS Inservice Testing Program Removal & Clarify
SR [Surveillance Requirement] Usage Rule Application to Section 5.5
Testing.'' The proposed change eliminates the PVNGS TS, Section 5.5.8,
to remove requirements duplicated in the American Society of Mechanical
Engineers Code for Operations and Maintenance of Nuclear Power Plants
(ASME OM Code) Code Case OMN-20, ``Inservice Test Frequency.''
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 revises Chapter 5, Administrative Controls,
Section 5.5, Programs and Manuals, by eliminating the Inservice
Testing Program specification. Requirements in the IST [Inservice
Testing] Program are removed, as they are duplicative of
requirements in the ASME OM Code, as clarified by Code Case OMN-20,
Inservice Test Frequency. Other requirements in Section 5.5.8,
Inservice Testing Program are eliminated because the NRC has
determined
[[Page 38717]]
their inclusion in the TS is contrary to regulations. A new defined
term, Inservice Testing Program, is added which references the
requirements of 10 CFR 50.55a(f).
Performance of inservice testing is not an initiator to any
accident previously evaluated. As a result, the probability of
occurrence of an accident is not significantly affected by the
proposed change. Inservice test periods under Code Case OMN-20 are
equivalent to the current testing period allowed by the TS with the
exception that testing periods greater than two years may be
extended by up to six months to facilitate test scheduling and
consideration of plant operating conditions that may not be suitable
for performance of the required testing. The testing period
extension will not affect the ability of the components to mitigate
any accident previously evaluated as the components are required to
be operable during the testing period extension. Performance of
inservice tests utilizing the allowances in Code Case OMN-20 will
not significantly affect the reliability of the tested components.
As a result, the availability of the affected components, as well as
their ability to mitigate the consequences of accidents previously
evaluated, is not affected.
Therefore, the proposed change does not involve a significant
increase in the probability or consequences of an accident
previously evaluated.
2. Does the proposed amendment create the possibility of a new
or different kind of accident from any accident previously
evaluated?
Response: No.
The proposed change does not alter the design or configuration
of the plant. The proposed change does not involve a physical
alteration of the plant; no new or different kind of equipment will
be installed. The proposed change does not alter the types of
inservice testing performed. In most cases, the frequency of
inservice testing is unchanged. However, the frequency of testing
would not result in a new or different kind of accident from any
previously evaluated since the testing methods are not altered.
Therefore, the proposed change does not create the possibility
of a new or different kind of accident from any accident previously
evaluated.
3. Does the proposed amendment involve a significant reduction
in a margin of safety?
Response: No.
The proposed change eliminates some requirements from the TS in
lieu of requirements in the ASME Code, as modified by use of Code
Case OMN-20. Compliance with the ASME Code is required by 10 CFR
50.55a. The proposed change also allows inservice tests with periods
greater than two years to be extended by six months to facilitate
test scheduling and consideration of plant operating conditions that
may not be suitable for performance of the required testing. The
testing period extension will not affect the ability of the
components to respond to an accident as the components are required
to be operable during the testing period extension. The proposed
change will eliminate the existing TS SR 3.0.3 allowance to defer
performance of missed inservice tests up to the duration of the
specified testing period, and instead will require an assessment of
the missed test on equipment operability. This assessment will
consider the effect on a margin of safety (equipment operability).
Should the component be inoperable, the Technical Specifications
provide actions to ensure that the margin of safety is protected.
The proposed change also eliminates a statement that nothing in the
ASME Code should be construed to supersede the requirements of any
TS. The NRC has determined that statement to be incorrect. However,
elimination of the statement will have no effect on plant operation
or 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
that review, it appears that the three standards of 10 CFR 50.92(c) are
satisfied. Therefore, the NRC staff proposes to determine that the
request for amendments involves no significant hazards consideration.
Attorney for licensee: Michael G. Green, Senior Regulatory Counsel,
Pinnacle West Capital Corporation, P.O. Box 52034, Mail Station 8695,
Phoenix, AZ 85072-2034.
NRC Branch Chief: Robert J. Pascarelli.
Entergy Nuclear Operations, Inc., Docket No. 50-271, Vermont Yankee
Nuclear Power Station (VY), Vernon, Vermont
Date of amendment request: May 1, 2017. A publicly-available
version is in ADAMS under Accession No. ML17124A429. This request was
supplemented by information submitted by the licensee by letter dated
June 13, 2017 (ADAMS Accession No. ML17166A234).
Description of amendment request: The proposed amendment would
extend the scheduled implementation date for Milestone 8 of the VY
Cyber Security Plan (CSP) to July 31, 2019, to support the
decommissioning status of VY.
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 CSP implementation schedule is
administrative in nature.
This proposed change does not alter accident analysis
assumptions, add any initiators, or affect the function of facility
systems or the manner in which systems are operated, maintained,
modified, tested, or Inspected. The proposed change does not require
any facility modifications which affect the performance capability
of the structures, systems, and components (SSCs) relied upon to
mitigate the consequences of postulated accidents and has no impact
on the probability or consequences of an accident previously
evaluated.
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 change to the CSP implementation schedule is
administrative in nature.
This proposed change does not alter accident analysis
assumptions, add any initiators, or affect the function of facility
systems or the manner in which systems are operated, maintained,
modified, tested, or inspected. The proposed change does not require
any facility modifications which affect the performance capability
of the SSCs 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, 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.
Plant safety margins are established through limiting conditions
for operation, limiting safety system settings, and safety limits
specified In the Technical Specifications. The proposed change to
the CSP implementation schedule is administrative in nature. In
addition, the milestone date delay for full implementation of the
CSP has no substantive impact because other measures, including
completing and maintaining interim Milestones 1 through 7, have been
taken which provide adequate protection during this period of time.
Because there is no change to established safety margins as a result
of this proposed change, no significant reduction in a margin of
safety is involved.
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: Ms. Susan Raimo, Senior Counsel, Entergy
Services, Inc., 101 Constitution Avenue
[[Page 38718]]
NW., Suite 200 East, Washington, DC 20001.
NRC Branch Chief: Bruce Watson.
FirstEnergy Nuclear Operating Company, Docket No. 50-440, Perry Nuclear
Power Plant, Unit No. 1, Lake County, Ohio
Date of amendment request: June 20, 2017. A publicly-available
version is in ADAMS under Accession No. ML17171A301.
Description of amendment request: The proposed amendment would
revise a surveillance requirement (SR) in Technical Specification
3.8.1, ``AC Sources--Operating,'' to clarify that the intent of the
surveillance is to verify that only the non-critical diesel generator
(DG) trips are bypassed on an emergency core cooling system initiation
signal. The proposed changes are consistent with Technical
Specification Task Force Improved Standard Technical Specifications
Change Traveler 400-A, Revision 1, ``Clarify SR on Bypass of DG
Automatic Trips.''
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 clarifies the purpose of SR 3.8.1.13, which
is to verify that non-critical automatic diesel generator (DG) trips
are bypassed in an accident. The DG automatic trips and their
bypasses are not initiators of any accident previously evaluated.
Therefore, the probability of any accident is not significantly
increased. The function of the DGs in mitigating accidents is not
changed. The revised SR continues to ensure the DGs will operate as
assumed in the accident analyses. Therefore, the consequences of any
accident previously evaluated are not affected.
Therefore, the proposed change does not involve a significant
increase in the probability or consequences of an accident
previously evaluated.
2. Does the proposed amendment create the possibility of a new
or different kind of accident from any accident previously
evaluated?
Response: No.
The proposed change clarifies the purpose of SR 3.8.1.13, which
is to verify that non-critical automatic DG trips are bypassed in an
accident. 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.
Thus, this change does not create the possibility of a new or
different kind of accident from any accident previously evaluated.
3. Does the proposed amendment involve a significant reduction
in a margin of safety?
Response: No.
The proposed change clarifies the purpose of SR 3.8.1.13, which
is to verify that non-critical automatic DG trips are bypassed in an
accident. Performance of the clarified SR will verify that the non-
critical trips are bypassed on simulated ECCS [emergency core
cooling system] actuation signals to ensure that actuation of a non-
critical trip does not take a DG out of service during an emergency.
The bypassing of the non-critical automatic DG trips will maintain
DG availability during an emergency so that it will be able to
perform its assumed safety function. As such, the safety function of
the DGs remains unaffected, so the change does not affect the margin
of safety.
Therefore, the proposed change does not involve a significant
reduction in a margin of safety.
The NRC staff has reviewed the licensee's analysis and, based on
this review, it appears that the three standards of 10 CFR 50.92(c) are
satisfied. Therefore, the NRC staff proposes to determine that the
amendment request involves no significant hazards consideration.
Attorney for licensee: David W. Jenkins, Attorney, FirstEnergy
Corporation, Mail Stop A-GO-15, 76 South Main Street, Akron, OH 44308.
NRC Branch Chief: David J. Wrona.
Omaha Public Power District, Docket No. 50-285, Fort Calhoun Station
(FCS), Unit No. 1, Washington County, Nebraska
Date of amendment request: June 9, 2017. A publicly-available
version is in ADAMS under Accession No. ML17160A405.
Description of amendment request: The proposed amendment would
delete Technical Specifications (TSs) 2.8.3(6), ``Spent Fuel Cask
Loading,'' and associated Figure 2-11, ``Limiting Burnup Criteria for
Acceptable Storage in Spent Fuel Cask''; TS 3.2 Table 3-5(24), ``Spent
Fuel Cask Loading''; TS 4.3.1.3, Design Features associated with spent
fuel casks; and portions of TS 3.2, Table 3-4(5), Footnote (4) on boron
concentration associated with cask loading. The deletion of the TS
sections will bring the FCS TSs into conformance with 10 CFR 50.68(c)
``Criticality accident requirements.''
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 simply bring[s] the [station's] technical
specifications into compliance with the current version of 10 CFR
50.68. There is no change to probability or consequences of any
accident previously evaluated.
Therefore, the proposed change does not involve a significant
increase in the probability or consequences of an accident
previously evaluated.
2. Does the proposed amendment create the possibility of a new
or different kind of accident from any accident previously
evaluated?
Response: No.
The proposed change does not alter [any] safety limits, or
safety analysis assumptions associated with the operation of the
plant. The proposed change does not introduce any new accident
initiators, nor does the change reduce or adversely affect the
capabilities of any plant structure or system in the performance of
its safety function.
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 does not alter the manner in which safety
limits or limiting safety system settings are determined. The safety
analysis acceptance criteria are not affected by the proposed
change. The proposed change does not change the design function of
any equipment assumed to operate in the event of an accident.
Therefore, the proposed change does not involve a significant
reduction in a margin of safety.
The NRC staff has reviewed the licensee's analysis and, based on
this review, it appears that the three standards of 10 CFR 50.92(c) are
satisfied. Therefore, the NRC staff proposes to determine that the
amendment request involves no significant hazards consideration.
Attorney for licensee: David A. Repka, Esq., Winston & Strawn, 1700
K Street NW., Washington, DC 20006-3817.
NRC Branch Chief: Douglas A. Broaddus.
Omaha Public Power District, Docket No. 50-285, Fort Calhoun Station
(FCS), Unit No. 1, Washington County, Nebraska
Date of amendment request: June 16, 2017. A publicly-available
version is in ADAMS under Accession No. ML17167A057.
Description of amendment request: The proposed amendment would
remove the FCS Cyber Security Plan (CSP) from the FCS Operating License
Condition.
Basis for proposed no significant hazards consideration
determination:
[[Page 38719]]
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 to remove the [FCS CSP] requirement 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
[SSCs] relied upon to mitigate the consequences of postulated
accidents, and has no impact on the probability or consequences of
an accident previously evaluated.
Therefore, the proposed change does not involve a significant
increase in the probability or consequences of an accident
previously evaluated.
2. Does the proposed amendment create the possibility of a new
or different kind of accident from any accident previously
evaluated?
Response: No.
The proposed change to remove the [FCS CSP] requirement 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 [SSCs] relied upon to mitigate the
consequences of postulated accidents, and has no impact on the
probability or consequences of an 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 amendment proposes the elimination of the CSP as set forth
in the CSP Implementation Schedule and associated regulatory
commitments. The elimination of the CSP does not involve
modifications to any safety-related SSCs. The proposed amendment is
based on the comparison of the risks at an operating nuclear power
reactor as opposed to a nuclear power reactor that has permanently
ceased operations and has removed all fuel from the reactor vessel.
The spectrum of possible accidents are significantly fewer and the
risk of an offsite radiological release is significantly lower for a
permanently defueled reactor.
Therefore, the proposed change does not involve a significant
reduction in a margin of safety.
The NRC staff has reviewed the licensee's analysis and, based on
this review, it appears that the three standards of 10 CFR 50.92(c) are
satisfied. Therefore, the NRC staff proposes to determine that the
amendment request involves no significant hazards consideration.
Attorney for licensee: David A. Repka, Esq., Winston & Strawn, 1700
K Street NW., Washington, DC 20006-3817.
NRC Branch Chief: Douglas A. Broaddus.
Southern Nuclear Operating Company, Inc., Docket Nos. 52-025 and 52-
026, Vogtle Electric Generating Plant (VEGP), Units 3 and 4, Burke
County, Georgia
Date of amendment request: June 23, 2017. A publicly-available
version is in ADAMS under Accession No. ML17179A171.
Description of amendment request: The requested amendment requires
changes to the Updated Final Safety Analysis Report (UFSAR) in the form
of departures from the plant-specific Design Control Document Tier 2
information and involves changes to the VEGP Units 3 and 4 COL Appendix
A, Technical Specifications (TS). Specifically, the proposed changes
revise plant-specific Tier 2 information to add the time delay assumed
in the safety analysis for the reactor trip on a safeguards actuation
(``S'') signal to UFSAR Table 15.0-4a. This is also reflected in the
proposed revision to TS 3.3.4, Reactor Trip System (RTS) Engineered
Safety Feature Actuation System (ESFAS) Instrumentation, to add a
surveillance requirement to verify the RTS response time for this ``S''
signal.
The request also includes proposed changes to TS 3.3.7, RTS Trip
Actuation Devices, to clarify that the requirements for reactor trip
breaker (RTB) undervoltage and shunt trip mechanisms apply only to in-
service RTBs. In addition, the request includes proposed changes to TS
3.3.9, ESFAS Manual Initiation, to correct the nomenclature for the
Chemical and Volume Control System, which is advertently stated as the
Chemical Volume and Control System.
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 NRC staff edits in square
brackets:
1. Does the proposed amendment involve a significant increase in
the probability or consequences of an accident previously evaluated?
Response: No.
The changes do not involve an interface with any [structure,
system, and component (SSC)] accident initiator or initiating
sequence of events, and thus, the probabilities of the accidents
evaluated in the plant-specific UFSAR are not affected. The proposed
changes do not involve a change to any mitigation sequence or the
predicted radiological releases due to postulated accident
conditions, thus, the consequences of the accidents evaluated in the
UFSAR are not affected.
Therefore, the proposed amendment does not involve a significant
increase in the probability or consequences of an accident
previously evaluated.
2. Does the proposed amendment create the possibility of a new
or different kind of accident from any accident previously
evaluated?
Response: No.
The proposed changes do not adversely affect any system or
design function or equipment qualification as the change does not
modify any SSCs that prevent safety functions from being performed.
The changes do not introduce a new failure mode, malfunction or
sequence of events that could adversely affect safety or safety-
related equipment.
Therefore, the proposed amendment does not create the
possibility of a new or different kind of accident from any accident
previously evaluated.
3. Does the proposed amendment involve a significant reduction
in a margin of safety?
Response: No.
The proposed changes would not affect any safety-related design
code, function, design analysis, safety analysis input or result, or
existing design/safety margin. No safety analysis or design basis
acceptance limit/criterion is challenged or exceeded by the
requested changes.
Therefore, the proposed amendment does not involve a significant
reduction in a margin of safety.
The NRC staff has reviewed the licensee's analysis and, based on
this review, it appears that the three standards of 10 CFR 50.92(c) are
satisfied. Therefore, the NRC staff proposes to determine that the
amendment request involves no significant hazards consideration.
Attorney for licensee: Mr. M. Stanford Blanton, Balch & Bingham
LLP, 1710 Sixth Avenue North Birmingham, AL 35203-2015.
NRC Branch Chief: Jennifer Dixon-Herrity.
III. Notice of Issuance of Amendments to Facility Operating Licenses
and Combined Licenses
During the period since publication of the last biweekly notice,
the Commission has issued the following amendments. The Commission has
determined for each of these amendments that the application complies
with the standards and requirements of the Atomic Energy Act of 1954,
as amended (the Act), and the Commission's rules and regulations. The
Commission has made appropriate findings as required by the Act and the
[[Page 38720]]
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.
Arizona Public Service Company, et al., Docket Nos. STN 50-528, STN 50-
529, and STN 50-530, Palo Verde Nuclear Generating Station (PVNGS),
Units 1, 2, and 3, Maricopa County, Arizona
Date of application for amendment: November 25, 2015, as
supplemented by letters dated January 29, June 30, October 6, November
9, and November 23, 2016; and March 3 and May 24, 2017.
Brief Description of amendment: The amendments revised the
Technical Specifications (TSs) for PVNGS, by modifying the requirements
to incorporate the results of an updated criticality safety analysis
for both new and spent fuel storage.
Date of issuance: July 28, 2017.
Effective date: As of the date of issuance and shall be implemented
within 90 days from the date of issuance.
Amendment Nos.: Unit 1--203, Unit 2--203, and Unit 3--203. A
publicly-available version is in ADAMS under Accession No. ML17188A412;
documents related to these amendments are listed in the Safety
Evaluation enclosed with the amendments.
Renewed Facility Operating License Nos. NPF-41, NPF-51, and NPF-74:
The amendments revised the Operating Licenses and TSs.
Date of initial notice in Federal Register: April 5, 2016 (81 FR
19644). The supplements dated June 30, October 6, November 9, and
November 23, 2016; and March 3 and May 24, 2017, provided additional
information that clarified the application, did not expand the scope of
the application as originally noticed, and did not change the NRC
staff's original proposed no significant hazards consideration
determination as published in the Federal Register.
The Commission's related evaluation of the amendments is contained
in a Safety Evaluation dated July 28, 2017.
No significant hazards consideration comments received: No.
Duke Energy Carolinas, LLC, Docket Nos. 50-413 and 50-414, Catawba
Nuclear Station, Units 1 and 2, York County, South Carolina
Date of application for amendments: December 15, 2016.
Brief description of amendments: The amendments modified Technical
Specification (TS) 3.6.3, ``Containment Isolation Valves,'' to add a
Note to TS Limiting Condition for Operation (LCO) 3.6.3 Required
Actions A.2, C.2, and E.2 to allow isolation devices that are locked,
sealed, or otherwise secured to be verified by use of administrative
means. The changes are consistent with NRC-approved Technical
Specifications Task Force (TSTF) Traveler TSTF-269-A, Revision 2,
``Allow administrative means of position verification for locked or
sealed valves.''
Date of issuance: July 21, 2017.
Effective date: These license amendments are effective as of their
date of issuance and shall be implemented within 120 days of issuance.
Amendment Nos.: 290 and 286. A publicly available version is in
ADAMS under Accession No. ML17165A441; documents related to these
amendments are listed in the Safety Evaluation enclosed with the
amendments.
Renewed Facility Operating License Nos. NPF-35 and NPF-52:
Amendments revised the licenses and TSs.
Date of initial notice in Federal Register: April 25, 2017 (82 FR
19098).
The Commission's related evaluation of the amendments is contained
in a Safety Evaluation dated July 21, 2017.
No significant hazards consideration comments received: No.
Duke Energy Carolinas, LLC, Docket Nos. 50-413 and 50-414, Catawba
Nuclear Station, Units 1 and 2, York County, South Carolina
Date of application for amendments: December 15, 2016.
Brief description of amendments: The amendments modified Technical
Specification (TS) 3.1.8, ``PHYSICS TESTS Exceptions,'' to allow the
numbers of channels required by the Limiting Condition of Operation
(LCO) section of TS 3.3.1, ``Reactor Trip System (RTS)
Instrumentation,'' to be reduced from ``4'' to ``3'' to allow one
nuclear instrumentation channel to be used as an input to the
reactivity computer for physics testing without placing the nuclear
instrumentation channel in a tripped condition. The changes are
consistent with Technical Specifications Task Force (TSTF) Traveler
TSTF-315-A, Revision 0, ``Reduce plant trips due to spurious signals to
the NIS [Nuclear Instrumentation System] during physics testing.''
Date of issuance: July 26, 2017.
Effective date: These license amendments are effective as of its
date of issuance and shall be implemented within 120 days of issuance.
Amendment Nos.: 291 (Unit 1) and 287 (Unit 2). A publicly-available
version is in ADAMS under Accession No. ML17172A428; documents related
to these amendments are listed in the Safety Evaluation enclosed with
the amendments.
Renewed Facility Operating License Nos. NPF-35 and NPF-52:
Amendments revised the licenses and TSs.
Date of initial notice in Federal Register: April 25, 2017 (82 FR
19098).
The Commission's related evaluation of the amendments is contained
in a Safety Evaluation dated July 26, 2017.
No significant hazards consideration comments received: No.
Energy Northwest, Docket No. 50-397, Columbia Generating Station
(Columbia), Benton County, Washington
Date of application for amendment: July 14, 2016, as supplemented
by letter dated July 5, 2017.
Brief description of amendment: The amendment changed the Columbia
Technical Specifications (TSs) consistent with TS Task Force (TSTF)
Standard Technical Specifications Change Traveler TSTF-545, Revision 3,
``TS Inservice Testing Program Removal & Clarify SR [Surveillance
Requirement] Usage Rule Application to Section 5.5 Testing,'' dated
October 21, 2015.
Date of issuance: July 24, 2017.
Effective date: As of its date of issuance and shall be implemented
within 60 days from the date of issuance.
Amendment No.: 243. A publicly-available version is in ADAMS under
Accession No. ML17187A257; documents related to this amendment
[[Page 38721]]
are listed in the Safety Evaluation enclosed with the amendment.
Renewed Facility Operating License No. NPF-21: The amendment
revised the Facility Operating License and TSs.
Date of initial notice in Federal Register: September 27, 2016 (81
FR 66304). The supplemental letter dated July 5, 2017, provided
additional information that clarified the application, did not expand
the scope of the application as originally noticed, and did not change
the staff's original proposed no significant hazards consideration
determination as published in the Federal Register.
The Commission's related evaluation of the amendment is contained
in a Safety Evaluation dated July 24, 2017.
No significant hazards consideration comments received: No.
Entergy Operations, Inc., Docket No. 50-382, Waterford Steam Electric
Station, Unit 3 (Waterford 3), St. Charles Parish, Louisiana
Date of amendment request: July 25, 2016.
Brief description of amendment: The amendment changed the Waterford
3 Technical Specifications (TSs) consistent with Technical
Specifications Task Force (TSTF) Standard Technical Specifications
Change Traveler TSTF-545, Revision 3, ``TS Inservice Testing Program
Removal & Clarify SR [Surveillance Requirement] Usage Rule Application
to Section 5.5 Testing,'' dated October 21, 2015.
Date of issuance: July 27, 2017.
Effective date: As of the date of issuance and shall be implemented
90 days from the date of issuance.
Amendment No.: 250. A publicly-available version is in ADAMS under
Accession No. ML17192A007; documents related to this amendment are
listed in the Safety Evaluation enclosed with the amendment.
Facility Operating License No. NPF-38: The amendment revised the
Facility Operating License and TSs.
Date of initial notice in Federal Register: November 8, 2016 (81 FR
78647).
The Commission's related evaluation of the amendment is contained
in a Safety Evaluation dated July 27, 2017.
No significant hazards consideration comments received: No.
NextEra Energy, Point Beach, LLC, Docket No. 50-266, Point Beach
Nuclear Plant (PBNP), Unit 1, Town of Two Creeks, Manitowoc County,
Wisconsin
Date amendment request: July 29, 2016, as supplemented by letter
dated April 20, 2017. Publicly-available versions of these documents
are in ADAMS under Accession Nos. ML16237A066 and ML17110A068,
respectively.
Brief description of amendments: The amendment consists of changes
to the technical specifications (TSs) for PBNP, Unit 1. The amendment
makes changes to TS 3.4.13, ``RCS Operational LEAKAGE,'' TS 5.5.8,
``Steam Generator (SG) Program,'' and TS 5.6.8, ``Steam Generator Tube
Inspection Report,'' in order to implement the H* (pronounced H-star)
alternate repair criteria on a permanent basis.
Date of issuance: July 27, 2017.
Effective date: As of the date of issuance and shall be implemented
within 90 days of issuance.
Amendment No.: 260. A publicly-available version is in ADAMS under
Accession No. ML17159A778; documents related to this amendment are
listed in the Safety Evaluation enclosed with the amendment.
Renewed Facility Operating License No. DPR-24: Amendment revised
the Facility Operating License and TSs.
Date of initial notice in Federal Register: December 6, 2016 (81 FR
87961). The supplemental letter dated April 20, 2017, provided
additional information that clarified the application, did not expand
the scope of the application as originally noticed, and did not change
the staff's original proposed no significant hazards consideration
determination as published in the Federal Register.
The Commission's related evaluation of the amendment is contained
in a Safety Evaluation dated July 27, 2017.
No significant hazards consideration comments received: No.
Omaha Public Power District, Docket No. 50-285, Fort Calhoun Station
(FCS), Unit 1, Washington County, Nebraska
Date of amendment request: September 2, 2016, as supplemented by
letters dated March 3 and April 5, 2017.
Brief description of amendment: The amendment revised the Nuclear
Radiological Emergency Response Plan for FCS for the plant condition
following permanent cessation of power operations and defueling to
reflect changes in the shift staffing and Emergency Response
Organization staffing.
Date of issuance: July 27, 2017.
Effective date: As of the date of issuance and shall be implemented
within 60 days from the date of issuance.
Amendment No.: 291. A publicly-available version is in ADAMS under
Accession No. ML17123A348; documents related to this amendment are
listed in the Safety Evaluation enclosed with the amendment.
Renewed Facility Operating License No. DPR-40: The amendment
revised the license.
Date of initial notice in Federal Register: November 8, 2016 (81 FR
78650). The supplemental letters dated March 3 and April 5, 2017,
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 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 July 27, 2017.
No significant hazards consideration comments received: No.
Omaha Public Power District, Docket No. 50-285, Fort Calhoun Station
(FCS), Unit 1, Washington County, Nebraska
Date of amendment request: September 28, 2016, as supplemented by
letter dated April 27, 2017.
Brief description of amendment: The amendment revised the Technical
Specifications (TSs) to make administrative changes to align staffing
for permanently defueled condition at FCS.
Date of issuance: July 28, 2017.
Effective date: As of the date of issuance and shall be implemented
within 90 days from the date of issuance.
Amendment No.: 292. A publicly-available version is in ADAMS under
Accession No. ML17165A465; documents related to this amendment are
listed in the Safety Evaluation enclosed with the amendment.
Renewed Facility Operating License No. DPR-40: The amendment
revised the Renewed Facility Operating License and TSs.
Date of initial notice in Federal Register: November 8, 2016 (81 FR
78650).
The supplemental letter dated April 27, 2017, provided additional
information that clarified the application, did not expand the scope of
the application as originally noticed, and did not change the 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 July 28, 2017.
No significant hazards consideration comments received: No.
[[Page 38722]]
Southern Nuclear Operating Company, Docket Nos. 52-025 and 52-026,
Vogtle Electric Generating Plant (VEGP), Units 3 and 4, Burke County,
Georgia
Date of amendment request: January 20, 2017, and supplemented by
letter dated June 6, 2017.
Description of amendment: The amendments consist of changes to the
VEGP Units 3 and 4 Updated Final Safety Analysis Report (UFSAR) in the
form of departures from plant-specific Design Control Document Tier 2
information, Combined License (COL) Appendix A Technical
Specifications, and COL Appendix C information. The departures consist
of in-containment refueling water storage tank (IRWST) minimum volume
changes in plant-specific UFSAR Table 14.3-2, COL Appendix A Technical
Specifications 3.5.6, 3.5.7 and 3.5.8 and Surveillance Requirements
3.5.6.2 and 3.5.8.2 and COL Appendix C (and associated plant-specific
Tier 1) Table 2.2.3-4. The changes restore the desired consistency of
these sections with the UFSAR IRWST minimum volume value in other
locations.
Date of issuance: July 6, 2017.
Effective date: As of the date of issuance and shall be implemented
within 30 days of issuance.
Amendment Nos.: 81 and 80. A publicly-available version is in ADAMS
under Accession No. ML17171A137; documents related to this amendment
are listed in the Safety Evaluation enclosed with the amendment.
Facility Combined Licenses No. NPF-91 and NPF-92: Amendment revised
the Facility Combined Licenses.
Date of initial notice in Federal Register: March 14, 2017 (82 FR
13662). The supplemental letter dated June 6, 2017, provided additional
information that clarified the application, did not expand the scope of
the application request as originally noticed, and did not change the
staff's original proposed no significant hazards consideration
determination as published in the Federal Register.
The Commission's related evaluation of the amendment is contained
in the Safety Evaluation dated July 6, 2017.
No significant hazards consideration comments received: No.
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: February 1, 2017, as supplemented by
letter dated May 17, 2017.
Brief description of amendments: The amendments revised Technical
Specification (TS) 3.6.4.3, ``Standby Gas Treatment (SGT) System,'' and
TS 3.7.3, ``Control Room Emergency Outside Air Supply (CREOAS)
System,'' by changing the run time of monthly surveillance requirements
for the standby gas treatment and control room emergency outside air
supply systems from 10 hours to 15 minutes. This change is consistent
with Technical Specifications Task Force (TSTF) Traveler TSTF-522,
Revision 0, ``Revise Ventilation System Surveillance Requirements to
Operate for 10 hours per Month,'' with minor variations. The notice of
availability and model safety evaluation of TSTF-522, Revision 0, were
published in the Federal Register on September 20, 2012 (77 FR 58421).
Date of issuance: July 28, 2017.
Effective date: As of the date of issuance and shall be implemented
within 60 days of issuance.
Amendment Nos.: 268 (Unit 1) and 250 (Unit 2). A publicly-available
version is in ADAMS under Accession No. ML17187A297; documents related
to these amendments are listed in the Safety Evaluation enclosed with
the amendments.
Renewed Facility Operating License Nos. NPF-14 and NPF-22: The
amendments revised the Renewed Facility Operating Licenses and TSs.
Date of initial notice in Federal Register: April 11, 2017 (82 FR
17461). The supplemental letter dated May 17, 2017, provided additional
information that clarified the application, did not expand the scope of
the application as originally noticed, and did not change the NRC
staff's original proposed no significant hazards consideration
determination as published in the Federal Register.
The Commission's related evaluation of the amendments is contained
in a Safety Evaluation dated July 28, 2017.
No significant hazards consideration comments received: No.
Virginia Electric and Power Company, Docket Nos. 50-280 and 50-281,
Surry Power Station, Units No. 1 and No. 2, Surry County, Virginia
Date of amendment request: July 14, 2016, as supplemented by
letters dated January 31, 2017, March 1, 2017 and March 10, 2017.
Brief description of amendments: The amendments would extend the
Technical Specification (TS) 3.14.B allowed outage time for one
inoperable emergency service water (ESW) pump from 7 to 14 days to
provide operational flexibility for ESW pump maintenance and repairs.
Date of issuance: July 28, 2017.
Effective date: As of the date of issuance and shall be implemented
within 60 days of issuance.
Amendment Nos.: 290 and 290. A publicly-available version is in
ADAMS under Accession No. ML17170A183; documents related to these
amendments are listed in the Safety Evaluation enclosed with the
amendments.
Facility Operating License No. NPF-4 and NPF-7: Amendments revised
the Facility Operating Licenses and TSs.
Date of initial notice in Federal Register: October 25, 2016 (81 FR
73443). The letters dated January 31, 2017, March 1, 2017 and March 10,
2017, provided additional information that clarified the application,
did not expand the scope of the application as originally noticed, and
did not change the staff's original proposed no significant hazards
consideration determination as published in the Federal Register.
The Commission's related evaluation of the amendment is contained
in a Safety Evaluation dated July 28, 2017.
No significant hazards consideration comments received: No.
Dated at Rockville, Maryland, this 4th day of August 2017.
For the Nuclear Regulatory Commission.
Anne T. Boland,
Director, Division of Operating Reactor Licensing, Office of Nuclear
Reactor Regulation.
[FR Doc. 2017-16998 Filed 8-14-17; 8:45 am]
BILLING CODE 7590-01-P