[Federal Register Volume 83, Number 108 (Tuesday, June 5, 2018)]
[Notices]
[Pages 26112-26119]
From the Federal Register Online via the Government Publishing Office [www.gpo.gov]
[FR Doc No: 2018-10982]
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NUCLEAR REGULATORY COMMISSION
[NRC-2018-0102]
Applications and Amendments to Facility Operating Licenses and
Combined Licenses Involving Proposed No Significant Hazards
Considerations and Containing Sensitive Unclassified Non-Safeguards
Information and Order Imposing Procedures for Access to Sensitive
Unclassified Non-Safeguards Information
AGENCY: Nuclear Regulatory Commission.
ACTION: License amendment request; notice of opportunity to comment,
request a hearing, and petition for leave to intervene; order imposing
procedures.
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SUMMARY: The U.S. Nuclear Regulatory Commission (NRC) received and is
considering approval of three amendment requests. The amendment
requests are for River Bend Station, Unit 1; Grand Gulf Nuclear
Station, Unit 1; and Browns Ferry Nuclear Plant, Units 1, 2, and 3. For
each amendment request, the NRC proposes to determine that they involve
no significant hazards consideration. Because each amendment request
contains sensitive unclassified non-safeguards information (SUNSI) an
order imposes procedures to obtain access to SUNSI for contention
preparation.
DATES: Comments must be filed by July 5, 2018. A request for a hearing
must be filed by August 6, 2018. Any potential party as defined in
Sec. 2.4 of title 10 of the Code of Federal Regulations (10 CFR) who
believes access to SUNSI is necessary to respond to this notice must
request document access by June 15, 2018.
ADDRESSES: You may submit comments by any of the following methods:
Federal Rulemaking website: Go to http://www.regulations.gov and search for Docket ID NRC-2018-0102. Address
questions about NRC dockets to Jennifer Borges; telephone: 301-287-
9127; email: [email protected]. For technical questions, contact
the individual listed in the FOR FURTHER INFORMATION CONTACT section of
this document.
Mail comments to: May Ma, Office of Administration, Mail
Stop: TWFN-7-A60M, U.S. Nuclear Regulatory Commission, Washington, DC
20555-0001.
For additional direction on obtaining information and submitting
comments, see ``Obtaining Information and Submitting Comments'' in the
SUPPLEMENTARY INFORMATION section of this document.
FOR FURTHER INFORMATION CONTACT: 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-2018-0102, facility name, unit
number(s),
[[Page 26113]]
plant docket number, application date, and subject when contacting the
NRC about the availability of information for this action. You may
obtain publicly-available information related to this action by any of
the following methods:
Federal Rulemaking website: Go to http://www.regulations.gov and search for Docket ID NRC-2018-0102.
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 is provided the
first time that it is mentioned in this document.
NRC's PDR: You may examine and purchase copies of public
documents at the NRC's PDR, Room O1-F21, One White Flint North, 11555
Rockville Pike, Rockville, Maryland 20852.
B. Submitting Comments
Please include Docket ID NRC-2018-0102, 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 NRC is publishing this 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 notice includes notices of amendments containing SUNSI.
III. Notice of Consideration of Issuance of Amendments to Facility
Operating Licenses and Combined Licenses, Proposed No Significant
Hazards Consideration Determination, and Opportunity for a Hearing
The Commission has made a proposed determination that the following
amendment requests involve no significant hazards consideration. Under
the Commission's regulations in 10 CFR 50.92, 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 a notice of issuance in the Federal
Register. If the Commission makes a final no significant hazards
consideration determination, any hearing will take place after
issuance. The Commission expects that the need to take this action will
occur very infrequently.
A. Opportunity to Request a Hearing and Petition for Leave To Intervene
Within 60 days after the date of publication of this notice, any
persons (petitioner) whose interest may be affected by this action may
file a request for a hearing and petition for leave to intervene
(petition) with respect to the action. Petitions shall be filed in
accordance with the Commission's ``Agency Rules of Practice and
Procedure'' in 10 CFR part 2. Interested persons should consult a
current copy of 10 CFR 2.309. The NRC's regulations are accessible
electronically from the NRC Library on the NRC's website at http://www.nrc.gov/reading-rm/doc-collections/cfr/. Alternatively, a copy of
the regulations is available at the NRC's Public Document Room, located
at One White Flint North, Room O1-F21, 11555 Rockville Pike (first
floor), Rockville, Maryland 20852. If a petition is filed, the
Commission or a presiding officer will rule on the petition and, if
appropriate, a notice of a hearing will be issued.
As required by 10 CFR 2.309(d) the petition should specifically
explain the reasons why intervention should be permitted with
particular reference to the following general requirements for
standing: (1) The name, address, and telephone number of the
petitioner; (2) the nature of the petitioner's right under the Act to
be made a party to the proceeding; (3) the nature and extent of the
petitioner's property, financial, or other interest in the proceeding;
and (4) the possible effect of any decision or order which may be
entered in the proceeding on the petitioner's interest.
In accordance with 10 CFR 2.309(f), the petition must also set
forth the specific contentions which the petitioner seeks to have
litigated in the proceeding. Each contention must consist of a specific
statement of the issue of law or fact to be raised or controverted. In
addition, the petitioner must provide a brief explanation of the bases
for the contention and a concise statement of the alleged facts or
expert opinion which support the contention and on which the petitioner
intends to rely in proving the contention at the hearing. The
petitioner must also provide references to the specific sources and
documents on which the petitioner intends to rely to support its
position on the issue. The petition must include sufficient information
to show that a genuine dispute exists with the
[[Page 26114]]
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 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
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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.
Entergy Louisiana, LLC, and Entergy Operations, Inc., Docket No. 50-
458, River Bend Station, Unit 1 (River Bend), West Feliciana Parish,
Louisiana
Date of amendment request: April 2, 2018. A publicly-available
version is in ADAMS under Accession No. ML18092B187.
Description of amendment request: This amendment request contains
sensitive unclassified non-safeguards information (SUNSI). The proposed
amendment would replace Technical Specification (TS) Figure 3.4.11-1,
``Minimum Temperature Required vs. RCS [Reactor Coolant System]
Pressure,'' curves, also known as the pressure and temperature limit
curves. The current TS figure is calculated for 34 Effective Full Power
Years (EFPY), and the proposed TS figure would provide for 54 EFPY. The
proposed TS figure includes new fluence values and material chemistry
information, and uses the new methodologies described in Licensing
Topical Report NEDO-33882, Revision 1, ``Pressure and Temperature
Limits Report (PTLR) Up to 54 Effective Full Power Years.''
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.
Basis: The proposed change to the River Bend reactor coolant
system (RCS) pressure/temperature (P/T) limits does not modify the
boundary, operating pressure, materials or seismic loading of the
reactor coolant system. The proposed change does adjust the P/T
limits for neutron irradiation effects to ensure that the Reactor
Pressure Vessel (RPV) fracture toughness is consistent with analysis
assumptions and NRC regulations. Changing the applicability of the
limits to 54 effective full power years (EFPY) will continue to
maintain appropriate limits for River Bend during the renewed
license term. The proposed limits are more bounding than the current
limits.
Therefore, it is concluded that this change does not
significantly increase 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.
Basis: The proposed change to the reactor pressure vessel
pressure-temperature limits does not involve any physical changes
(installing new equipment or modifying existing equipment). The
change does not affect the assumed accident performance of any
structure, system or component previously evaluated. These revised
limits are in compliance with the brittle fracture requirements of
[10 CFR part 50] Appendix G. The proposed change does not introduce
any new modes of system operation or failure mechanisms.
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.
Basis: The proposed change, which corrects a non-conservative
TS, does not exceed or alter a setpoint, design basis or safety
limit. 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: Anna Vinson Jones, Senior Counsel/Legal
Department, Entergy Services, Inc., 101 Constitution Avenue NW, Suite
200 East, Washington, DC 20001.
NRC Branch Chief: Robert J. Pascarelli.
Entergy Operations, Inc. (Entergy); System Energy Resources, Inc.;
Cooperative Energy, A Mississippi Electric Cooperative; and Entergy
Mississippi, Inc., Docket No. 50-416, Grand Gulf Nuclear Station, Unit
No. 1, Claiborne County, Mississippi
Date of amendment request: March 26, 2018. A publicly-available
version is in ADAMS under Accession No. ML18085A579.
Description of amendment request: This amendment request contains
sensitive unclassified non-safeguards information (SUNSI). The proposed
amendment would revise the Updated Final Safety Analysis Report (UFSAR)
descriptions for the replacement of the Turbine First Stage Pressure
(TFSP) output signals with Power Range Neutron Monitoring System
(PRNMS) output signals. During June 2014, Entergy implemented
Engineering Change (EC) 49880 in accordance with
[[Page 26116]]
10 CFR 50.59, ``Changes, tests, and experiments,'' that replaced the
use of the TFSP instruments with the PRNMS to measure reactor power. On
December 9, 2016, the NRC issued NRC Inspection Report 05000416/
2016007. In this inspection report, the NRC issued non-cited violation
050000416/2016007-02, which identified that Entergy failed to obtain a
license amendment prior to implementing the proposed change.
Specifically, modification EC 40880 eliminated the TFSP instrument
signals to the Reactor Protection System and replaced the signals with
average power range monitor signals. The NRC concluded that the change
reduced the diversity and resulted in a more than minimal increase in
the likelihood of occurrence of a malfunction of a structure, system,
or component (SSC) important to safety.
Entergy has determined that the proposed change requires NRC
approval per 10 CFR 50.59(c)(2). Entergy concluded that the plant
modification is potentially a reduction in diversity based on the Grand
Gulf Nuclear Station, Unit 1, licensing basis. As such, the potential
reduction in diversity is considered to be a change that results in
more than a minimal increase in the likelihood of occurrence of a
malfunction of an SSC important to safety previously evaluated in the
UFSAR.
The proposed amendment would eliminate the potential for a
transient caused by the mechanical failure of the TFSP sensing lines
and instruments. It would also eliminate process delays in the steam
lines, as the PRNMS voltage output signals are based on average power
range monitoring signals, a direct and immediate measurement of neutron
flux. The PRNMS signals are divisionally separated, safety-related, and
provide reliability, quality, and defense-in-depth that the TFSP
sensing lines and instruments could not provide. The replacement of the
TFSP output signals with the PRNMS output signals enhances plant safety
and improves reliability.
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 modification does not result in a change to the
safety related functions including Low Power Setpoint (LPSP) and
High Power Setpoint (HPSP), Turbine Stop Valve (TSV) closure and
Turbine Control Valve (TCV) fast closure scram enable/bypass, and
End of Cycle Recirculation Pump Trip (EOC-RPT) enable/bypass. The
accidents potentially affected by the TFSP instrumentation are the
turbine trip event (UFSAR Section 15.2.3), generator load rejection
event (UFSAR Section 15.2.2), control rod drop accident (UFSAR
Section 15.4.9) and rod withdrawal error (UFSAR Section 15.4.1). The
proposed use of PRNMS signal outputs as inputs to the trip units
will maintain the safety related functions credited in the evaluated
events. Furthermore, the proposed modification makes no changes to
the existing PRNM system inputs, system software or hardware
architecture.
Overall protection system performance will remain within the
bounds of the previously performed accident analyses since the
proposed modification does not change the Reactor Protection System
(RPS) or the Rod Control and Information System (RCIS). The same RPS
and RCIS instrumentation will continue to be used. The protection
systems will continue to function in a manner consistent with the
plant design basis. The proposed modifications will not adversely
affect accident initiators or precursors nor adversely alter the
design assumptions and conditions of the facility or the manner in
which the plant is operated and maintained with respect to such
initiators or precursors.
The proposed modification will not prevent the capability of
structures, systems, and components (SSCs) to perform their intended
functions for mitigating the consequences of an accident and meeting
applicable acceptance limits.
Therefore, operation of the facility in accordance with the
proposed amendment would 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 use of PRNMS for determining reactor power will ensure that
the protective functions EOC-RPT, TSV closure and TCV fast closure
direct scram functions, and the rod pattern controller (RPC) and Rod
Withdrawal Limiter functions credited in the safety analyses are
maintained. With these automatic functions maintained, the proposed
modification does not create the possibility of a new or different
kind of accident from any accident previously evaluated in the
UFSAR.
No new accident scenarios, transient precursors, failure
mechanisms, or limiting single failures will be introduced as a
result of the proposed modification. No new or different accidents
result from the proposed modification. The proposed modification
will not alter the performance of the RPS, RCIS and PRNMS.
Thus, 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 modification does not alter the manner in which
safety limits, safety setpoints, or limiting conditions for
operation are determined. The PRNMS hardware and software are not
changed by this modification. The modified system responds to a loss
of power, and a restoration of power, in the same way as the TFSP
system would have responded. The proposed modification makes no
changes to the PRNMS, RPS or RCIS human-system interfaces. The
equipment credited to perform a safety function has been designed
and installed to the applicable quality standards and maintained the
required redundancy. The proposed modification is expected to
provide an improvement in accuracy for the determination of the low
power setpoint and high power setpoint in terms of reactor power.
The replacement of the TFSP output signals with the PRNMS output
signals does not reduce the diversity of the RPS trip functions by
use of a more direct measurement of power given the additional
diverse capabilities available. The proposed modification maintains
conservative margins between Analytical Limits, Allowable Values and
the Nominal Trip Setpoints.
The proposed change does not impact accident offsite dose,
containment pressure or temperature, Emergency Core Cooling System
settings, Reactor Core Isolation Cooling System settings or RPS
settings, or other parameter that could affect a margin of safety.
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: Anna Vinson Jones, Senior Counsel/Legal
Department, Entergy Services, Inc., 101 Constitution Avenue NW, Suite
200 East, Washington, DC 20001.
NRC Branch Chief: Robert J. Pascarelli.
Tennessee Valley Authority, Docket Nos. 50-259, 50-260, and 50-296,
Browns Ferry Nuclear Plant, Units 1, 2, and 3 (BFN), Limestone County,
Alabama
Date of amendment request: February 23, 2018, as supplemented by
letter dated March 7, 2018. Publicly-available versions are in ADAMS
under Accession Nos. ML18079B140 and ML18067A495, respectively.
Description of amendment request: This amendment request contains
sensitive unclassified non-safeguards information (SUNSI). The proposed
amendments would allow operation of BFN in the expanded Maximum
[[Page 26117]]
Extended Load Line Limit Analysis Plus (MELLLA+) operating domain.
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 operation in the MELLLA+ operating domain does not
significantly increase the probability or consequences of an
accident previously evaluated.
The probability (frequency of occurrence) of Design Basis
Accidents (DBAs) occurring is not affected by the MELLLA+ operating
domain because BFN continues to comply with the regulatory and
design basis criteria established for plant equipment. There is no
change in consequences of postulated accidents when operating in the
MELLLA+ operating domain compared to the operating domain previously
evaluated. The results of accident evaluations remain within the NRC
approved acceptance limits.
The spectrum of postulated transients has been investigated and
is shown to meet the plant's currently licensed regulatory criteria.
Continued compliance with the Safety Limit Minimum Critical Power
Ratio (SLMCPR) will be confirmed on a cycle-specific basis
consistent with the criteria accepted by the NRC.
Challenges to the reactor coolant pressure boundary were
evaluated for the MELLLA+ operating domain conditions (pressure,
temperature, flow, and radiation) and were found to meet their
acceptance criteria for allowable stresses and overpressure margin.
Challenges to the containment were evaluated and the containment
and its associated cooling systems continue to meet the current
licensing basis. The calculated post-Loss-of-Coolant Accident (LOCA)
suppression pool temperature remains acceptable.
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 operation in the MELLLA+ operating domain does not
create the possibility of a new or different kind of accident from
any previously evaluated.
Equipment that could be affected by the MELLLA+ operating domain
has been evaluated. No new operating mode, safety-related equipment
lineup, accident scenario, or equipment failure mode was identified.
The full spectrum of accident considerations has been evaluated and
no new or different kind of accident has been identified. The
MELLLA+ operating domain uses developed technology, and applies it
within the capabilities of existing plant safety-related equipment
in accordance with the regulatory criteria (including NRC-approved
codes, standards and methods). No new accident or event precursor
has been identified.
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 operation in the MELLLA+ operating domain does not
involve a significant reduction in the margin of safety.
The MELLLA+ operating domain affects only design and operational
margins. Challenges to the fuel, reactor coolant pressure boundary,
and containment were evaluated for the MELLLA+ operating domain
conditions. Fuel integrity is maintained by meeting existing design
and regulatory limits. The calculated loads on affected structures,
systems, and components, including the reactor coolant pressure
boundary, will remain within their design allowables for design
basis event categories. No NRC acceptance criterion is exceeded. The
BFN configuration and responses to transients and postulated
accidents do not result in exceeding the presently approved NRC
acceptance limits.
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 Dr., WT 6A-K, Knoxville, Tennessee 37902.
NRC Acting Branch Chief: Brian W. Tindell.
Order Imposing Procedures for Access to Sensitive Unclassified Non-
Safeguards Information for Contention Preparation
Entergy Louisiana, LLC, and Entergy Operations, Inc., Docket No. 50-
458, River Bend Station, Unit 1, West Feliciana Parish, Louisiana
Entergy Operations, Inc.; System Energy Resources, Inc.; Cooperative
Energy, A Mississippi Electric Cooperative; and Entergy Mississippi,
Inc., Docket No. 50-416, Grand Gulf Nuclear Station, Unit 1, Claiborne
County, Mississippi
Tennessee Valley Authority, Docket Nos. 50-259, 50-260, and 50-296,
Browns Ferry Nuclear Plant, Unit Nos. 1, 2, and 3, Limestone County,
Alabama
A. This Order contains instructions regarding how potential parties
to this proceeding may request access to documents containing Sensitive
Unclassified Non-Safeguards Information (SUNSI).
B. Within 10 days after publication of this notice of hearing and
opportunity to petition for leave to intervene, any potential party who
believes access to SUNSI is necessary to respond to this notice may
request access to SUNSI. A ``potential party'' is any person who
intends to participate as a party by demonstrating standing and filing
an admissible contention under 10 CFR 2.309. Requests for access to
SUNSI submitted later than 10 days after publication of this notice
will not be considered absent a showing of good cause for the late
filing, addressing why the request could not have been filed earlier.
C. The requester shall submit a letter requesting permission to
access SUNSI to the Office of the Secretary, U.S. Nuclear Regulatory
Commission, Washington, DC 20555-0001, Attention: Rulemakings and
Adjudications Staff, and provide a copy to the Associate General
Counsel for Hearings, Enforcement and Administration, Office of the
General Counsel, U.S. Nuclear Regulatory Commission, Washington, DC
20555-0001. The expedited delivery or courier mail address for both
offices is: U.S. Nuclear Regulatory Commission, 11555 Rockville Pike,
Rockville, Maryland 20852. The email address for the Office of the
Secretary and the Office of the General Counsel are
[email protected] and [email protected], respectively.\1\ The
request must include the following information:
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\1\ While a request for hearing or petition to intervene in this
proceeding must comply with the filing requirements of the NRC's
``E-Filing Rule,'' the initial request to access SUNSI under these
procedures should be submitted as described in this paragraph.
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(1) A description of the licensing action with a citation to this
Federal Register notice;
(2) The name and address of the potential party and a description
of the potential party's particularized interest that could be harmed
by the action identified in C.(1); and
(3) The identity of the individual or entity requesting access to
SUNSI and the requester's basis for the need for the information in
order to meaningfully participate in this adjudicatory proceeding. In
particular, the request must explain why publicly available versions of
the information requested would not be sufficient to provide the basis
and specificity for a proffered contention.
D. Based on an evaluation of the information submitted under
paragraph
[[Page 26118]]
C.(3) the NRC staff will determine within 10 days of receipt of the
request whether:
(1) There is a reasonable basis to believe the petitioner is likely
to establish standing to participate in this NRC proceeding; and
(2) The requestor has established a legitimate need for access to
SUNSI.
E. If the NRC staff determines that the requestor satisfies both
D.(1) and D.(2) above, the NRC staff will notify the requestor in
writing that access to SUNSI has been granted. The written notification
will contain instructions on how the requestor may obtain copies of the
requested documents, and any other conditions that may apply to access
to those documents. These conditions may include, but are not limited
to, the signing of a Non-Disclosure Agreement or Affidavit, or
Protective Order \2\ setting forth terms and conditions to prevent the
unauthorized or inadvertent disclosure of SUNSI by each individual who
will be granted access to SUNSI.
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\2\ Any motion for Protective Order or draft Non-Disclosure
Affidavit or Agreement for SUNSI must be filed with the presiding
officer or the Chief Administrative Judge if the presiding officer
has not yet been designated, within 30 days of the deadline for the
receipt of the written access request.
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F. Filing of Contentions. Any contentions in these proceedings that
are based upon the information received as a result of the request made
for SUNSI must be filed by the requestor no later than 25 days after
receipt of (or access to) that information. However, if more than 25
days remain between the petitioner's receipt of (or access to) the
information and the deadline for filing all other contentions (as
established in the notice of hearing or opportunity for hearing), the
petitioner may file its SUNSI contentions by that later deadline.
G. Review of Denials of Access.
(1) If the request for access to SUNSI is denied by the NRC staff
after a determination on standing and requisite need, the NRC staff
shall immediately notify the requestor in writing, briefly stating the
reason or reasons for the denial.
(2) The requester may challenge the NRC staff's adverse
determination by filing a challenge within 5 days of receipt of that
determination with: (a) The presiding officer designated in this
proceeding; (b) if no presiding officer has been appointed, the Chief
Administrative Judge, or if he or she is unavailable, another
administrative judge, or an Administrative Law Judge with jurisdiction
pursuant to 10 CFR 2.318(a); or (c) if another officer has been
designated to rule on information access issues, with that officer.
(3) Further appeals of decisions under this paragraph must be made
pursuant to 10 CFR 2.311.
H. Review of Grants of Access. A party other than the requester may
challenge an NRC staff determination granting access to SUNSI whose
release would harm that party's interest independent of the proceeding.
Such a challenge must be filed within 5 days of the notification by the
NRC staff of its grant of access and must be filed with: (a) The
presiding officer designated in this proceeding; (b) if no presiding
officer has been appointed, the Chief Administrative Judge, or if he or
she is unavailable, another administrative judge, or an Administrative
Law Judge with jurisdiction pursuant to 10 CFR 2.318(a); or (c) if
another officer has been designated to rule on information access
issues, with that officer.
If challenges to the NRC staff determinations are filed, these
procedures give way to the normal process for litigating disputes
concerning access to information. The availability of interlocutory
review by the Commission of orders ruling on such NRC staff
determinations (whether granting or denying access) is governed by 10
CFR 2.311.\3\
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\3\ Requesters should note that the filing requirements of the
NRC's E-Filing Rule (72 FR 49139; August 28, 2007, as amended at 77
FR 46562; August 3, 2012), apply to appeals of NRC staff
determinations (because they must be served on a presiding officer
or the Commission, as applicable), but not to the initial SUNSI
request submitted to the NRC staff under these procedures.
---------------------------------------------------------------------------
I. The Commission expects that the NRC staff and presiding officers
(and any other reviewing officers) will consider and resolve requests
for access to SUNSI, and motions for protective orders, in a timely
fashion in order to minimize any unnecessary delays in identifying
those petitioners who have standing and who have propounded contentions
meeting the specificity and basis requirements in 10 CFR part 2. The
attachment to this Order summarizes the general target schedule for
processing and resolving requests under these procedures.
It is so ordered.
Dated at Rockville, Maryland, this 17th day of May, 2018.
For the Nuclear Regulatory Commission.
Annette L. Vietti-Cook,
Secretary of the Commission.
Attachment 1--General Target Schedule for Processing and Resolving
Requests for Access to Sensitive Unclassified Non-Safeguards Information
in This Proceeding
------------------------------------------------------------------------
Day Event/activity
------------------------------------------------------------------------
0...................... Publication of Federal Register notice of
hearing and opportunity to petition for leave
to intervene, including order with
instructions for access requests.
10..................... Deadline for submitting requests for access to
Sensitive Unclassified Non[dash]Safeguards
Information (SUNSI) with information:
supporting the standing of a potential party
identified by name and address; and describing
the need for the information in order for the
potential party to participate meaningfully in
an adjudicatory proceeding.
60..................... Deadline for submitting petition for
intervention containing: (i) Demonstration of
standing; and (ii) all contentions whose
formulation does not require access to SUNSI
(+25 Answers to petition for intervention; +7
petitioner/requestor reply).
20..................... U.S. Nuclear Regulatory Commission (NRC) staff
informs the requester of the staff's
determination whether the request for access
provides a reasonable basis to believe
standing can be established and shows need for
SUNSI. (NRC staff also informs any party to
the proceeding whose interest independent of
the proceeding would be harmed by the release
of the information.) If NRC staff makes the
finding of need for SUNSI and likelihood of
standing, NRC staff begins document processing
(preparation of redactions or review of
redacted documents).
25..................... If NRC staff finds no ``need'' or no likelihood
of standing, the deadline for petitioner/
requester to file a motion seeking a ruling to
reverse the NRC staff's denial of access; NRC
staff files copy of access determination with
the presiding officer (or Chief Administrative
Judge or other designated officer, as
appropriate). If NRC staff finds ``need'' for
SUNSI, the deadline for any party to the
proceeding whose interest independent of the
proceeding would be harmed by the release of
the information to file a motion seeking a
ruling to reverse the NRC staff's grant of
access.
30..................... Deadline for NRC staff reply to motions to
reverse NRC staff determination(s).
[[Page 26119]]
40..................... (Receipt +30) If NRC staff finds standing and
need for SUNSI, deadline for NRC staff to
complete information processing and file
motion for Protective Order and draft Non-
Disclosure Affidavit. Deadline for applicant/
licensee to file Non-Disclosure Agreement for
SUNSI.
A...................... If access granted: issuance of presiding
officer or other designated officer decision
on motion for protective order for access to
sensitive information (including schedule for
providing access and submission of
contentions) or decision reversing a final
adverse determination by the NRC staff.
A + 3.................. Deadline for filing executed Non-Disclosure
Affidavits. Access provided to SUNSI
consistent with decision issuing the
protective order.
A + 28................. Deadline for submission of contentions whose
development depends upon access to SUNSI.
However, if more than 25 days remain between
the petitioner's receipt of (or access to) the
information and the deadline for filing all
other contentions (as established in the
notice of opportunity to request a hearing and
petition for leave to intervene), the
petitioner may file its SUNSI contentions by
that later deadline.
A + 53................. (Contention receipt +25) Answers to contentions
whose development depends upon access to
SUNSI.
A + 60................. (Answer receipt +7) Petitioner/Intervenor reply
to answers.
>A + 60................ Decision on contention admission.
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[FR Doc. 2018-10982 Filed 6-4-18; 8:45 am]
BILLING CODE 7590-01-P