[Federal Register Volume 83, Number 25 (Tuesday, February 6, 2018)]
[Notices]
[Pages 5277-5284]
From the Federal Register Online via the Government Publishing Office [www.gpo.gov]
[FR Doc No: 2018-01706]
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NUCLEAR REGULATORY COMMISSION
[NRC-2018-0011]
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 Nine Mile Point Nuclear Station, Unit 2; R.E. Ginna
Nuclear Power Plant; and Hope Creek Generating Station. 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 March 8, 2018. A request for a hearing
must be filed by April 9, 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 February 16, 2018.
ADDRESSES: You may submit comments by any of the following methods
(unless this document describes a different method for submitting
comments on a specific subject):
Federal Rulemaking website: Go to http://www.regulations.gov and search for Docket ID NRC-2018-0011. 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: May Ma, Office of Administration, Mail
Stop: OWFN-2-A13, 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: Shirley Rohrer, Office of Nuclear
Regulatory Regulation, U.S. Nuclear Regulatory Commission, Washington,
DC 20555-0001; telephone: 301-415-5411, email: [email protected].
SUPPLEMENTARY INFORMATION:
I. Obtaining Information and Submitting Comments
A. Obtaining Information
Please refer to Docket ID NRC-2018-0011, facility name, unit
number(s), plant docket number, application date, and subject when
contacting the NRC
[[Page 5278]]
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-2018-0011.
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-2018-0011, 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 applicant or licensee on
a material issue of law or fact. Contentions must be
[[Page 5279]]
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 on the NRC's
public website at http://www.nrc.gov/site-help/e-
[[Page 5280]]
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.
Exelon Generation Company, LLC, Docket No. 50-410, Nine Mile Point
Nuclear Station (NMP2), Unit 2, Oswego County, New York
Date of amendment request: November 3, 2017. A publicly-available
version is in ADAMS under Accession No. ML17307A019.
Description of amendment request: This amendment request contains
sensitive unclassified non-safeguards information (SUNSI). The
amendment would revise the safety limit (SL) minimum critical power
ratios (MCPRs) in Section 2.1.1, ``Reactor Core SLs,'' of the NMP2,
Technical Specifications.
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 derivation of the cycle specific Safety Limit Minimum
Critical Power Ratios (SLMCPRs) for incorporation into the Technical
Specifications (TS), and their use to determine cycle specific
thermal limits, has been performed using the methodology discussed
in NEDE-24011-P-A, ``General Electric Standard Application for
Reactor Fuel,'' Revision 25.
The basis of the SLMCPR calculation is to ensure that during
normal operation and during abnormal operational transients, at
least 99.9% of all fuel rods in the core do not experience
transition boiling if the limit is not violated. The new SLMCPRs
preserve the existing margin to transition boiling.
The MCPR safety limit is reevaluated for each reload using NRC-
approved methodologies. The analyses for NMP2, Cycle 17, have
concluded that a two-recirculation loop MCPR safety limit of >=1.17,
based on the application of Global Nuclear Fuel's NRC-approved MCPR
safety limit methodology, will ensure that this acceptance criterion
is met. For single recirculation loop operation, a MCPR safety limit
of >=1.17 also ensures that this acceptance criterion is met. The
MCPR operating limits are presented and controlled in accordance
with the NMP2 Core Operating Limits Report (COLR).
The requested TS changes do not involve any plant modifications
or operational changes that could affect system reliability or
performance or that could affect the probability of operator error.
The requested changes do not affect any postulated accident
precursors, do not affect any accident mitigating systems, and do
not introduce any new accident initiation mechanisms.
Therefore, the proposed TS changes do not involve a significant
increase in the probability or consequences of an accident
previously evaluated.
2. Does the proposed amendment create the possibility of a new
or different kind of accident from any accident previously
evaluated?
Response: No.
The SLMCPR is a TS numerical value, calculated to ensure that
during normal operation and during abnormal operational transients,
at least 99.9% of all fuel rods in the core do not experience
transition boiling if the limit is not violated. The new SLMCPRs are
calculated using NRC-approved methodology discussed in NEDE-24011-P-
A, ``General Electric Standard Application for Reactor Fuel,''
Revision 25. The proposed changes do not involve any new modes of
operation, any changes to setpoints, or any plant modifications. The
proposed revised MCPR safety limits have been shown to be acceptable
for Cycle 17 operation. The core operating limits will continue to
be developed using NRC-approved methods. The proposed MCPR safety
limits or methods for establishing the core operating limits do not
result in the creation of any new precursors to an accident.
Therefore, this 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.
There is no significant reduction in the margin of safety
previously approved by the NRC as a result of the proposed change to
the SLMCPRs. The new SLMCPRs are calculated using methodology
discussed in NEDE-24011-P-A, ``General Electric Standard Application
for Reactor Fuel,'' Revision 25. The SLMCPRs ensure that during
normal operation and during abnormal operational transients, at
least 99.9% of all fuel rods in the core do not experience
transition boiling if the limit is not violated, thereby preserving
the fuel cladding integrity.
Therefore, the proposed TS changes do not involve a significant
reduction in the margin of safety previously approved by the NRC.
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: Tamra Domeyer, Associate General Counsel,
Exelon Generation Company, LLC, 4300 Winfield Road, Warrenville, IL
60555.
NRC Branch Chief: James G. Danna.
[[Page 5281]]
Exelon Generation Company, LLC, Docket No. 50-244, R. E. Ginna Nuclear
Power Plant (Ginna), Wayne County, New York
Date of amendment request: November 16, 2017. A publicly-available
version is in ADAMS under Accession No. ML17321A107.
Description of amendment request: This amendment request contains
sensitive unclassified non-safeguards information (SUNSI). The
amendment would revise the Ginna's Technical Specifications for
selected Reactor Trip System (RTS) and Engineered Safety Feature
Actuation System (ESFAS) instrumentation channels. The change would
allow selected RTS (Table 3.3.1-1) and ESFAS instrumentation channels
(Table 3.3.2-1) to be bypassed during surveillance testing.
Additionally, the change would allow RTS and ESFAS input relays to be
excluded from the Channel Operational Test. The change would allow
testing of Nuclear Instrumentation System power range functions, which
are part of the RTS, with a permanently installed bypass capability,
while other RTS and ESFAS functions will be capable of being bypassed
utilizing permanent connections in the racks to connect a portable test
box.
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 Reactor Trip System (RTS) and Engineered Safety Feature
Actuation System (ESFAS) provide plant protection and are part of
the accident mitigation response. The RTS and ESFAS functions do not
themselves act as a precursor or an initiator for any transient or
design basis accident; therefore, the proposed change does not
significantly increase the probability of any accident previously
evaluated.
The structural and functional integrity of the RTS and ESFAS, or
any other plant system, is unaffected. The proposed change does not
alter or prevent the ability of structures, systems, and components
to perform their intended function to mitigate the consequences of
an initiating event within the assumed acceptance limits.
Surveillance testing in the bypass condition will not cause any
design or analysis acceptance criteria to be exceeded.
Under the proposed change, the channel being tested may be
bypassed. The number of available channels with one channel in
bypass for testing will remain the same as the number of channels
available when testing in trip. The number of channels to trip will
be unchanged when testing in bypass while the number of channels to
trip is reduced to one when testing in trip. Although there may be a
slight increase in the possibility that the failure of a channel
could prevent the actuation of a function (because testing in bypass
could result in two-out-of-two logic while testing in trip would
have resulted in one-out-of-two logic), testing in bypass will
reduce the vulnerability to inadvertent actuation of a function
while maintaining the required number of channels to trip. The
impact of using bypass test capability upon nuclear safety has been
previously evaluated by the NRC and determined to be acceptable in
WCAP-10271-P-A and its supplements. Thus, testing in bypass when all
channels are operable does not involve a significant increase in the
probability or consequences of an accident previously evaluated.
Under the proposed change, the channel being tested may be
bypassed when another channel is concurrently inoperable and in a
tripped condition. As a result, one channel in bypass and another in
trip leaves one-out-of-two operable channels to initiate the
protective function (if the initial logic is two-out-of-four) or
one-out-of-one operable channels to initiate the protective function
(if the initial logic was two-out-of-three). Thus, testing in bypass
with one channel inoperable does not involve a significant increase
in the probability or consequences of an accident previously
evaluated.
Implementation of the bypass testing capability does not affect
the integrity of the fission product barriers utilized for
mitigation of radiological dose consequences as a result of an
accident. Plant response as modeled in the safety analyses is
unaffected. Hence, the releases used as input to the dose
calculations are unchanged from those previously assumed.
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.
Surveillance testing in bypass does not affect accident
initiation sequences or response scenarios as modeled in the safety
analyses. No new operating configuration is being imposed by the
surveillance testing in bypass that would create a new failure
scenario. The RTS and ESFAS will continue to have the same setpoints
after the proposed change is implemented. In addition, no new
failure modes are being created for any plant equipment. The bypass
test instrumentation has been designed to applicable regulatory and
industry standards. Fault conditions, failure detection, reliability
and equipment qualification have been considered. The modifications
do not result in any new or different accident scenarios.
The types of accidents defined in the UFSAR [Updated Final
Safety Analysis Report] continue to represent the credible spectrum
of events to be analyzed which determine safe plant operation.
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.
No safety analyses were changed or modified as a result of the
proposed TS change to reflect installed bypass test capability. The
proposed change does not alter the manner in which safety limits,
limiting safety system settings, or limiting conditions for
operation are determined. Margins associated with the current safety
analyses acceptance criteria are unaffected. The current safety
analyses remain bounding since their conclusions are not affected by
performing surveillance testing in bypass. The safety systems
credited in the safety analyses will continue to be available to
perform their mitigation functions.
Implementation of testing in bypass results in an overall
improvement in safety because the capability to test the channels in
bypass will reduce the potential for an inadvertent reactor trip or
safeguards actuation due to a failure or spurious transient in a
redundant channel.
Therefore, the proposed change does not result in 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: Tamra Domeyer, Associate General Counsel,
Exelon Generation Company, LLC, 4300 Winfield Road, Warrenville, IL
60555.
NRC Branch Chief: James G. Danna.
PSEG Nuclear LLC, Docket No. 50-354, Hope Creek Generating Station
(HCGS), Salem County, New Jersey
Date of amendment request: November 9, 2017. A publicly-available
version is in ADAMS under Accession No. ML17317B320.
Description of amendment request: This amendment request contains
sensitive unclassified non-safeguards information (SUNSI). The
amendment would revise the HCGS Technical Specifications (TSs).
Specifically, the amendment would revise the safety limit minimum
critical power ratio (SLMCPR) for two recirculation loop operation and
single recirculation loop operation based on the HCGS Cycle 22 specific
analysis.
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
[[Page 5282]]
consequences of an accident previously evaluated?
Response: No.
The required SLMCPRs for HCGS Cycle 22 are calculated using NRC-
approved methodology. The SLMCPR values, contained in TS Section 2.1
(``Safety Limits''), ensure at least 99.9% of all fuel rods in the
core do not experience transition boiling during normal operation
and analyzed transients, preserving fuel cladding integrity. The
proposed change to the SLMCPR values ensures this criterion
continues to be met, and therefore does not increase the probability
or consequences of an accident previously evaluated. In addition, no
plant hardware or operational changes are required with this
proposed change.
Therefore, the proposed change does not involve a significant
increase in the probability or consequences of an accident
previously evaluated.
2. Does the proposed amendment create the possibility of a new
or different kind of accident from any accident previously
evaluated?
Response: No.
The required SLMCPRs for HCGS Cycle 22 are calculated using NRC-
approved methodology. The SLMCPR values, contained in TS Section
2.1, ensure at least 99.9% of all fuel rods in the core do not
experience transition boiling during normal operation and analyzed
transients. The proposed change to the SLMCPR values does not
involve any plant hardware or operational changes and does not
create any new precursors to an accident.
Therefore, the proposed changes do not create the possibility of
a new or different kind of accident from any previously evaluated.
3. Does the proposed amendment involve a significant reduction
in a margin of safety?
Response: No.
The required SLMCPRs for HCGS Cycle 22 are calculated using NRC-
approved methodology. The SLMCPR values, contained in TS Section
2.1, ensure at least 99.9% of all fuel rods in the core do not
experience transition boiling during normal operation and analyzed
transients, preserving fuel cladding integrity. The revised SLMCPR
values ensure this criterion continues to be met. In addition, the
proposed change to the SLMCPR values does not adversely affect the
design basis function or performance of a structure, system, or
component as described in the HCGS UFSAR [Updated Final Safety
Analysis Report].
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: Jeffrie J. Keenan, PSEG Nuclear LLC--N21,
P.O. Box 236, Hancocks Bridge, NJ 08038.
NRC Branch Chief: James G. Danna.
Order Imposing Procedures for Access to Sensitive Unclassified Non-
Safeguards Information for Contention Preparation
Exelon Generation Company, LLC, Docket No. 50-410, Nine Mile Point
Nuclear Station, Unit 2, Oswego County, New York
Exelon Generation Company, LLC, Docket No. 50-244, R.E. Ginna Nuclear
Power Plant, Wayne County, New York
PSEG Nuclear LLC, Docket No. 50-354, Hope Creek Generating Station,
Salem County, New Jersey
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 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.
---------------------------------------------------------------------------
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.
[[Page 5283]]
(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 24th of January, 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-Safeguards
Information (SUNSI) with
information: Supporting the
standing of a potential party
identified by name and address;
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).
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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[[Page 5284]]
[FR Doc. 2018-01706 Filed 2-5-18; 8:45 am]
BILLING CODE 7590-01-P