[Federal Register Volume 79, Number 39 (Thursday, February 27, 2014)]
[Notices]
[Pages 11143-11151]
From the Federal Register Online via the Government Printing Office [www.gpo.gov]
[FR Doc No: 2014-04302]


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NUCLEAR REGULATORY COMMISSION

[NRC-2014-0029]


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; opportunity to comment, request a 
hearing, and petition for leave to intervene; order.

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SUMMARY: The U.S. Nuclear Regulatory Commission (NRC) received and is 
considering approval of six amendment requests. The amendment requests 
are for Palo Verde Nuclear Generating Station, Units 1, 2, and 3; 
Catawba Nuclear Station, Units 1 and 2; McGuire Nuclear Station, Units 
1 and 2; Indian Point Nuclear Generating, Units 1, 2, and 3; Palisades 
Nuclear Plant; and Vermont Yankee Nuclear Power Station. For each 
amendment request, the NRC proposes to determine that they involve no 
significant hazards consideration. In addition, each amendment request 
contains sensitive unclassified non-safeguards information (SUNSI).

DATES: Comments must be filed by March 31, 2014. A request for a 
hearing must be filed by April 28, 2014. 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 March 10, 2014.

ADDRESSES: You may submit comment by any of the following methods 
(unless this document describes a different method for submitting 
comments on a specific subject):
     Federal rulemaking Web site: Go to http://www.regulations.gov and search for Docket ID NRC-2014-0029. Address 
questions about NRC dockets to Carol Gallagher; telephone: 301-287-
3422; email: Carol.Gallagher@nrc.gov.
     Mail comments to: Cindy Bladey, Chief, Rules, 
Announcements, and Directives Branch (RADB), Office of Administration, 
Mail Stop: 3WFN-06-A44MP, U.S. Nuclear Regulatory Commission, 
Washington, DC 20555-0001.
    For additional direction on accessing information and submitting 
comments, see ``Accessing Information and Submitting Comments'' in the 
SUPPLEMENTARY INFORMATION section of this document.

SUPPLEMENTARY INFORMATION:

I. Accessing Information and Submitting Comments

A. Accessing Information

    Please refer to Docket ID NRC-2014-0029 when contacting the NRC 
about the availability of information regarding this document. You may 
access publicly-available information related to this action by the 
following methods:
     Federal Rulemaking Web site: Go to http://www.regulations.gov and search for Docket ID NRC-2014-0029.
     NRC's Agencywide Documents Access and Management System 
(ADAMS): You may access publicly available documents online in the NRC 
Library 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 pdr.resource@nrc.gov. The ADAMS accession number 
for each document referenced in this notice (if that document is 
available in ADAMS) is provided the first time that a document is 
referenced.
     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-2014-0029 in the subject line of your

[[Page 11144]]

comment submission, in order to ensure that the NRC is able to make 
your comment submission available to the public in this docket.
    The NRC cautions you not to include identifying or contact 
information that you do not want to be publicly disclosed in your 
comment submission. The NRC posts all comment submissions at http://www.regulations.gov as well as entering the comment submissions into 
ADAMS. The NRC does not routinely edit comment submissions to remove 
identifying or contact information.
    If you are requesting or aggregating comments from other persons 
for submission to the NRC, then you should inform those persons not to 
include identifying or contact information that they do not want to be 
publicly disclosed in their comment submission. Your request should 
state that the NRC does not routinely edit comment submissions to 
remove such information before making the comment submissions available 
to the public or entering the comment submissions into ADAMS.

II. 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.

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 should 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. Should the 
Commission take action prior to the expiration of either the comment 
period or the notice period, it will publish in the Federal Register a 
notice of issuance. Should the Commission make 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.
    Within 60 days after the date of publication of this notice, any 
person(s) whose interest may be affected by this action may file a 
request for a hearing and a petition to intervene with respect to 
issuance of the amendment to the subject facility operating license or 
combined license. Requests for a hearing and petitions for leave to 
intervene shall be filed in accordance with the Commission's ``Agency 
Rules of Practice and Procedure'' in 10 CFR Part 2. Interested 
person(s) should consult a current copy of 10 CFR 2.309, which is 
available at the NRC's PDR, located at One White Flint North, Room O1-
F21, 11555 Rockville Pike (first floor), Rockville, Maryland 20852. The 
NRC's regulations are accessible electronically from the NRC Library on 
the NRC's Web site at http://www.nrc.gov/reading-rm/doc-collections/cfr/. If a request for a hearing or petition for leave to intervene is 
filed within 60 days, the Commission or a presiding officer designated 
by the Commission or by the Chief Administrative Judge of the Atomic 
Safety and Licensing Board Panel, will rule on the request and/or 
petition; and the Secretary or the Chief Administrative Judge of the 
Atomic Safety and Licensing Board will issue a notice of a hearing or 
an appropriate order.
    As required by 10 CFR 2.309, a petition for leave to intervene 
shall set forth with particularity the interest of the petitioner in 
the proceeding, and how that interest may be affected by the results of 
the proceeding. The petition should specifically explain the reasons 
why intervention should be permitted with particular reference to the 
following general requirements: (1) The name, address, and telephone 
number of the requestor or petitioner; (2) the nature of the 
requestor's/petitioner's right under the Act to be made a party to the 
proceeding; (3) the nature and extent of the requestor's/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 requestor's/petitioner's interest. The petition must 
also set forth the specific contentions which the requestor/petitioner 
seeks to have litigated at 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 
requestor/petitioner shall 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 requestor/
petitioner intends to rely in proving the contention at the hearing. 
The requestor/petitioner must also provide references to those specific 
sources and documents of which the petitioner is aware and on which the 
requestor/petitioner intends to rely to establish those facts or expert 
opinion. The petition must include sufficient information to show that 
a genuine dispute exists with the applicant on a material issue of law 
or fact. Contentions shall be limited to matters within the scope of 
the amendment under consideration. The contention must be one which, if 
proven, would entitle the requestor/petitioner to relief. A requestor/
petitioner who fails to satisfy these requirements 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, 
and have the opportunity to participate fully in the conduct of the 
hearing.
    If a hearing is requested, and the Commission has not made a final

[[Page 11145]]

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 decide 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 held 
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 any amendment.
    All documents filed in NRC adjudicatory proceedings, including a 
request for hearing, a petition for leave to intervene, 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 participating under 10 CFR 2.315(c), 
must be filed in accordance with the NRC's E-Filing rule (72 FR 49139; 
August 28, 2007). 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. 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 hearing.docket@nrc.gov, or by 
telephone at 301-415-1677, to request (1) a digital identification (ID) 
certificate, which allows the participant (or its counsel or 
representative) to digitally sign documents and access the E-Submittal 
server for any proceeding in which it is participating; and (2) advise 
the Secretary that the participant will be submitting a request or 
petition for hearing (even in instances in which the participant, or 
its counsel or representative, already holds an NRC-issued digital ID 
certificate). Based upon this information, the Secretary will establish 
an electronic docket for the hearing in this proceeding if the 
Secretary has not already established an electronic docket.
    Information about applying for a digital ID certificate is 
available on the NRC's public Web site at  http://www.nrc.gov/site-help/e-submittals/apply-certificates.html. System requirements for 
accessing the E-Submittal server are detailed in the NRC's ``Guidance 
for Electronic Submission,'' which is available on the agency's public 
Web site at http://www.nrc.gov/site-help/e-submittals.html. 
Participants may attempt to use other software not listed on the Web 
site, but should note that the NRC E-Filing system does not support 
unlisted software, and the NRC Meta System Help Desk will not be able 
to offer assistance in using unlisted software.
    If a participant is electronically submitting a document to the NRC 
in accordance with the E-Filing rule, the participant must file the 
document using the NRC's online, Web-based submission form. In order to 
serve documents through the Electronic Information Exchange System, 
users will be required to install a Web browser plug-in from the NRC's 
Web site. Further information on the Web-based submission form, 
including the installation of the Web browser plug-in, is available on 
the NRC's public Web site at http://www.nrc.gov/site-help/e-submittals.html.
    Once a participant has obtained a digital ID certificate and a 
docket has been created, the participant can then submit a request for 
hearing or petition for leave to intervene. Submissions should be in 
Portable Document Format (PDF) in accordance with the NRC guidance 
available on the NRC's public Web site at http://www.nrc.gov/site-help/e-submittals.html. A filing is considered complete at the time the 
documents are submitted through the NRC 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 
documents on those participants separately. Therefore, applicants and 
other participants (or their counsel or representative) must apply for 
and receive a digital ID certificate before a hearing request/petition 
to intervene is filed so that they can obtain access to the document 
via the E-Filing system.
    A person filing electronically using the agency's adjudicatory E-
Filing system may seek assistance by contacting the NRC Meta System 
Help Desk through the ``Contact Us'' link located on the NRC's Web site 
at http://www.nrc.gov/site-help/e-submittals.html, by email at 
MSHD.Resource@nrc.gov, or by a toll-free call at 1-866-672-7640. The 
NRC Meta System Help Desk is available between 8 a.m. and 8 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 
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, Sixteenth 
Floor, One White Flint North, 11555 Rockville Pike, Rockville, 
Maryland, 20852, Attention: Rulemaking and Adjudications Staff. 
Participants filing a document 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 
http://ehd1.nrc.gov/ehd/, unless excluded pursuant to an order of the 
Commission, or the presiding officer. Participants are requested not to 
include personal privacy information, such as social security numbers, 
home addresses, or home phone numbers in their filings, unless an NRC 
regulation or other law requires submission of such information. 
However, a request to intervene will require including information on 
local residence in order to demonstrate a proximity assertion of 
interest in the proceeding. With respect to copyrighted works, except 
for limited excerpts that serve the purpose of the adjudicatory filings 
and would

[[Page 11146]]

constitute a Fair Use application, participants are requested not to 
include copyrighted materials in their submission.
    Petitions for leave to intervene must be filed no later than 60 
days from the date of publication of this notice. Requests for hearing, 
petitions for leave to intervene, and motions for leave to file new or 
amended contentions that are filed after the 60-day 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)-(iii).
    For further details with respect to this amendment action, see the 
application for amendment which is available for public inspection at 
the NRC's PDR, located at One White Flint North, Room O1-F21, 11555 
Rockville Pike (first floor), Rockville, Maryland 20852. Publicly 
available documents created or received at the NRC are accessible 
electronically through ADAMS in the NRC Library at http://www.nrc.gov/reading-rm/adams.html. If you do not have access to ADAMS or if there 
are problems in accessing the documents located in ADAMS, contact the 
PDR's Reference staff at 1-800-397-4209, 301-415-4737, or by email to 
pdr.resource@nrc.gov.
Arizona Public Service Company, et al., Docket No. 50-528, 50-529, and 
50-530, Palo Verde Nuclear Generating Station, Units 1, 2, and 3, 
Maricopa County, Arizona
    Date of amendment request: November 20, 2013, which is publicly 
available in ADAMS under Accession No. ML13329A036, as supplemented by 
letter dated November 20, 2013, portions of which are publicly 
available in ADAMS under Accession Nos. ML13329A700 and ML13365A207.
    Description of amendment request: This amendment request contains 
sensitive unclassified non-safeguards information (SUNSI). The proposed 
amendment would modify the Palo Verde Nuclear Generating Station, Units 
1, 2, and 3, moderator temperature coefficient (MTC) technical 
specification (TS) surveillance requirements (SR) associated with 
implementation of WCAP-16011-P-A, ``Startup Test Activity Reduction 
Program,'' February 2005, as described in Technical Specification Task 
Force (TSTF) change traveler TSTF-486, Revision 2, ``Revise MTC 
Surveillance for Startup Test Activity Reduction (STAR) Program (WCAP-
16011).'' The NRC staff published a notice of opportunity for comment 
in the Federal Register on July 27, 2007 (72 FR 41360), on possible 
amendments adopting TSTF-486, Revision 2, including a model safety 
evaluation and model no significant hazards consideration (NSHC) 
determination, using the consolidated line item improvement process 
(CLIIP). The NRC staff subsequently issued a notice of availability of 
the models for referencing in license amendment applications in the 
Federal Register on September 6, 2007 (72 FR 51259). The licensee 
affirmed the applicability of the model NSHC determination in its 
application dated November 20, 2013.
    Additionally, the proposed amendment would eliminate the 
measurement of an end-of-cycle (EOC) MTC if the beginning-of-cycle 
(BOC) measurements are within a given tolerance to the predicted value 
as described in TSTF-406, Revision 2, ``Predicting End-of-Cycle MTC and 
Deleting Need for End-of-Cycle MTC Verification.'' Regarding TSTF-406, 
Revision 2, the licensee included a proposed NSHC in the license 
amendment request.
    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. Each of the two items described above is addressed 
individually under each of the three standards, as presented below:

    1. Do the proposed changes involve a significant increase in the 
probability or consequences of an accident previously evaluated?

TSTF-486

    Response: No.
    The proposed change generically implements MTC SR changes 
associated with implementation of WCAP-16011-P-A, STAR Program. 
WCAP-16011-P-A describes methods to reduce the time required for 
startup testing. The consequences of an accident after adopting 
TSTF-486 are no different than the consequences of an accident prior 
to adoption.
    Therefore, this change does not involve a significant increase 
in the probability or consequences of an accident previously 
evaluated.

TSTF-406

    Response: No.
    A change is proposed to eliminate the measurement of end-of-
cycle (EOC) moderator temperature coefficient (MTC) if the 
beginning-of-cycle (BOC) measurements are within a given tolerance 
to the predicted value. MTC is not an initiator of any accident 
previously evaluated. Consequently, the probability of an accident 
previously evaluated is not significantly increased.
    The EOC MTC value is an important assumption in determining the 
consequences of accidents previously evaluated. The analysis 
presented in the Topical Report determined that the EOC MTC will be 
within limits if the BOC measured MTC values are within a given 
tolerance of the measured values. Therefore, the EOC MTC will 
continue to be within limits and the consequences of accidents will 
continue to be as previously evaluated. Therefore, the consequences 
of an accident previously evaluated are not significantly increased 
by this change.
    Based on the above, the proposed amendment does not involve a 
significant increase in the probability or consequences of an 
accident previously evaluated.
    2. Do the proposed changes create the possibility of a new or 
different kind of accident from any accident previously evaluated?

TSTF-486

    Response: No.
    The proposed change does not involve a physical alteration of 
the plant (no new or different type of equipment will be installed) 
or a change in the methods governing normal plant operation. The 
proposed change will not introduce new failure modes or effects and 
will not, in the absence of other unrelated failures, lead to an 
accident whose consequences exceed the consequences of accidents 
previously analyzed.
    Thus, this change does not create the possibility of a new or 
different kind of accident from any accident previously evaluated.

TSTF-406

    Response: No.
    A change is proposed to eliminate the measurement of EOC MTC if 
the BOC measurements are within a given tolerance to the predicted 
value. The proposed change does not involve a physical alteration of 
the plant (no new or different type of equipment will be installed) 
or a change in the methods governing normal plant operation.
    Based on the above, the proposed amendment does not create the 
possibility of a new or different kind of accident from any accident 
previously evaluated.
    3. Do the proposed changes involve a significant reduction in a 
margin of safety?

TSTF-486

    Response: No.
    TSTF-486 provides the means and standardized wording for 
[Combustion Engineering (CE) Standard Technical Specification (STS)] 
plants implementing the previously approved WCAP-16011-P-A alternate 
MTC verification at startup. MTC is a parameter controlled in the 
licensee's TS, including surveillance requirements. As stated 
previously WCAP-16011-P-A describes methods to reduce the time 
required for startup testing. The changes to NUREG-1432 proposed by 
TSTF-486 have been reviewed for and found to be consistent with the 
current NUREG-1432 and WCAP-16011-P-A.
    Therefore, the proposed changes are acceptable and do not 
involve a significant reduction in a margin of safety.

TSTF-406

    Response: No.

[[Page 11147]]

    A change is proposed to eliminate the measurement of EOC MTC if 
the BOC measurements are within a given tolerance to the predicted 
value. The Topical Report concluded that the risk of not measuring 
the EOC MTC is acceptably small provided that the BOC measured 
values are within a specific tolerance of the predicted values.
    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: Michael G. Green, Associate General 
Counsel--Nuclear and Environmental, Pinnacle West Capital Corporation, 
P.O. Box 52034, Mail Stop 7602, Phoenix, Arizona, 85072-2034.
    NRC Branch Chief: Michael T. Markley.
Duke Energy Carolinas, LLC, Docket Nos. 50-413 and 50-414, Catawba 
Nuclear Station, Units 1 and 2, York County, South Carolina; and Docket 
Nos. 50-369 and 50-370, McGuire Nuclear Station, Units 1 and 2, 
Mecklenburg County, North Carolina
    Date of amendment request: November 14, 2013. A publicly available 
version is available in ADAMS under Accession No. ML13325B142.
    Description of amendment request: This amendment request contains 
sensitive unclassified non-safeguards information (SUNSI). The 
amendments would revise Methodology Report DPC-NE-3001-P, Revision 1, 
``Multidimensional Reactor Transients and Safety Analysis Physics 
Parameters Methodology.''
    Basis for proposed no significant hazards consideration 
determination: As required by 10 CFR 50.91(a), the licensee has 
provided its analysis of the issue of no significant hazards 
consideration, which is presented below:

    1. Does the proposed amendment involve a significant increase in 
the probability or consequences of an accident previously evaluated?
    Response: No.
    The proposed amendments involving methodology report DPC-NE-
3001-P, Multidimensional Reactor Transients and Safety Analysis 
Physics Parameters Methodology, support the use of revised 
methodologies for simulating the Updated Final Safety Analysis 
Report (UFSAR) Chapter 15 events characterized by multidimensional 
reactor transients, and for systematically confirming that reload 
physics parameters important to UFSAR Chapter 15 transients and 
accidents are bounded by values assumed in the licensing analyses. 
The methodology report revision will be approved by the NRC prior to 
implementation. The proposed amendments will have no impact upon the 
probability of occurrence of any design basis accident. The proposed 
amendments will not affect the performance of any plant equipment 
used to mitigate the consequences of an analyzed accident. There 
will be no significant impact on the source term or pathways assumed 
in accidents previously evaluated. No analysis assumptions will be 
violated and there will be no adverse effects on offsite or onsite 
dose as the result of an accident.
    Therefore, the proposed amendments do not involve a significant 
increase in the probability or consequences of an accident 
previously evaluated.
    2. Does the proposed amendment create the possibility of a new 
or different kind of accident from any accident previously 
evaluated?
    Response: No.
    The proposed amendments do not change the methods governing 
normal plant operation; nor are the methods utilized to respond to 
plant transients altered. In addition, the proposed methodology 
changes will not create the potential for any new initiating events 
or transients to occur in the actual physical plant.
    Therefore, the proposed amendments do 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 the margin of safety?
    Response: No.
    Margin of safety is related to the confidence in the ability of 
the fission product barriers to perform their design functions 
during and following an accident. These barriers include the fuel 
cladding, the reactor coolant system, and the containment system. 
The proposed methodology revision will assure the acceptability of 
analytical limits under normal, transient, and accident conditions. 
The use of the proposed methodology revision once it has been 
approved by the NRC will ensure that all applicable design and 
safety limits are satisfied such that the fission product barriers 
will continue to perform their design functions.
    Therefore, the proposed amendments do not involve a significant 
reduction in a margin of safety.
    Based on the preceding discussion, Duke Energy concludes that 
the proposed amendments do not involve a significant hazards 
consideration under the standards set forth in 10 CFR 50.92(c), and, 
accordingly, a finding of ``no significant hazards consideration'' 
is justified.

    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: Lara S. Nichols, Associate General Counsel, 
Duke Energy Corporation, 526 South Church Street--EC07H, Charlotte, 
North Carolina 28202.
    NRC Branch Chief: Robert J. Pascarelli.
Entergy Nuclear Operations, Inc., Docket Nos. 50-03, 50-247, and 50-
286, Indian Point Nuclear Generating, Units 1, 2, and 3, Westchester 
County, New York
    Date of amendment request: August 20, 2013. A publicly available 
version is available in ADAMS under Accession No. ML13239A447.
    Description of amendment request: This amendment request contains 
sensitive unclassified non-safeguards information (SUNSI). The 
amendment would modify the operating license, pursuant to Section 161A 
of the Atomic Energy Act, to permit the licensee's security personnel 
to possess and use weapons, devices, ammunition, or other firearms, 
notwithstanding state, local, and certain federal firearms laws that 
may prohibit such use. The NRC refers to this authority as ``stand-
alone preemption authority.'' The licensee is seeking stand-alone 
preemption authority for standard weapons presently in use at the 
Indian Point facility in accordance with the Indian Point security 
plans, namely semi-automatic assault rifles and extended magazines. The 
weapons that are the subject of this amendment request do not include 
enhanced weapons.
    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[y] accident previously 
evaluated?
    Response: No.
    The LAR [license amendment request] does not require any plant 
modifications, alter the plant configuration, require new plant 
equipment to be installed, alter accident analysis assumptions, add 
any initiators, or affect the function of plant systems or the 
manner in which systems are operated, maintained, modified, tested, 
or inspected.
    The proposed change adds a sentence to the IPEC [Indian Point 
Energy Center] licenses to reflect the Section 161A preemption 
authority granted by the Commission. The change is administrative 
and has no impact on the probability or consequences of an[y] 
accident previously evaluated.
    Therefore, it is concluded that this change does not involve a 
significant increase in the probability or consequences of an[y] 
accident previously evaluated.

[[Page 11148]]

    2. Does the proposed change create the possibility of a new or 
different kind of accident from any accident previously evaluated?
    Response: No.
    The LAR does not require any plant modifications, alter the 
plant configuration, require new plant equipment to be installed, 
alter accident analysis assumptions, add any initiators, or affect 
the function of plant systems or the manner in which systems are 
operated, maintained, modified, tested, or inspected.
    The proposed change adds a sentence to the IPEC licenses to 
reflect the Section 161A preemption authority granted by the 
Commission. The change is administrative and has no impact on the 
possibility or [of] a new or different kind of accident from any 
accident previously evaluated.
    Therefore, it is concluded that this change does not create the 
possibility of a new or different kind of accident from any accident 
previously evaluated.
    3. Does the proposed change involve a significant reduction in a 
margin of safety?
    Response: No.
    The LAR does not require any plant modifications, alter the 
plant configuration, require new plant equipment to be installed, 
alter accident analysis assumptions, add any initiators, or affect 
the function of plant systems or the manner in which systems are 
operated, maintained, modified, tested, or inspected.
    Plant safety margins are established through Limiting Conditions 
for Operation, Limiting Safety System Settings and Safety limits 
specified in the Technical Specifications. Because there is no 
change to these established safety margins, the proposed change does 
not involve a significant reduction in a margin of safety.
    The proposed change adds a sentence to the IPEC licenses to 
reflect the Section 161A preemption authority granted by the 
Commission. The change is administrative and does not involve a 
significant reduction in a margin of safety.
    Therefore, the proposed change does not involve a significant 
reduction in a margin of safety.

    The NRC staff has reviewed the licensee's analysis and, based on 
this review, it appears that the three standards of 10 CFR 50.92(c) are 
satisfied. Therefore, the NRC staff proposes to determine that the 
amendment request involves no significant hazards consideration.
    Attorney for licensee: Ms. Jeanne Cho, Assistant General Counsel, 
Entergy Nuclear Operations, Inc., 440 Hamilton Avenue, White Plains, 
New York 10601.
    NRC Branch Chief: Benjamin G. Beasley.

Entergy Nuclear Operations, Inc., Docket No. 50-255, Palisades Nuclear 
Plant (PNP), Van Buren County, Michigan

    Date of amendment request: December 12, 2012, supplemented by 
letters dated February 21, September 30, October 24, and December 2, 
2013; the publicly-available version of each letter are available in 
ADAMS under Accession Nos. ML12348A455, ML13079A090, ML13273A469, 
ML13298A044, and ML13336A649.
    Description of amendment request: This amendment request contains 
sensitive unclassified non-safeguards information (SUNSI). The proposed 
amendment would provide the NRC's approval for adoption of a new fire 
protection licensing basis which complies with the requirements in 
Sec. Sec.  50.48(a) and 50.48(c); and the guidance in Regulatory Guide 
(RG) 1.205, Revision 1, ``Risk-Informed, Performance Based Fire 
Protection for Existing Light-Water Nuclear Power Plants.'' This 
amendment request also follows the guidance in Nuclear Energy Institute 
(NEI) 04-02, Revision 2, ``Guidance for Implementing a Risk-Informed, 
Performance-Based Fire Protection Program Under 10 CFR 50.48(c).'' Upon 
approval, the PNP's fire protection program will transition to a new 
Risk-Informed, Performance-Based (RI-PB) alternative in accordance with 
10 CFR 50.48(c), which incorporates by reference the National Fire 
Protection Association Standard 805 (NFPA 805). The NFPA 805 fire 
protection program will supersede the current fire protection program 
licensing basis in accordance with 10 CFR Part 50, Appendix R. 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.
    Operation of PNP in accordance with the proposed amendment does 
not result in a significant increase the probability or consequences 
of accidents previously evaluated. The proposed amendment does not 
affect accident initiators or precursors as described in the PNP 
Updated Final Safety Analysis Report (UFSAR), nor does it adversely 
alter design assumptions, conditions, or configurations of the 
facility, and it does not adversely impact the ability of 
structures, systems, or components (SSCs) to perform their intended 
function to mitigate the consequences of an initiating event within 
the assumed acceptance limits. The proposed changes do not affect 
the way in which safety related systems perform their functions as 
required by the accident analysis. The SSCs required to safely shut 
down the reactor and to maintain it in a safe shutdown condition 
will remain capable of performing their design functions.
    The purpose of the proposed amendment is to permit PNP to adopt 
a new risk-informed, performance based fire protection licensing 
basis that complies with the requirements of 10 CFR 50.48(a) and 
(c), as well as the guidance in RG 1.205. The NRC considers that 
NFPA 805 provides an acceptable methodology and performance criteria 
for licensees to identify fire protection requirements that are an 
acceptable alternative to the 10 CFR Part 50, Appendix R, fire 
protection features (69 FR 33536; June 16, 2004). Engineering 
analyses, including engineering evaluations, probabilistic safety 
assessments, and fire modeling calculations, have been performed to 
demonstrate that the performance based requirements of NFPA 805 have 
been met.
    The NFPA 805, taken as a whole, provides an acceptable 
alternative for satisfying General Design Criterion 3 (GDC 3) of 
Appendix A to 10 CFR Part 50, meets the underlying intent of the 
NRC's existing fire protection regulations and guidance, and 
achieves defense-in-depth along with the goals, performance 
objectives, and performance criteria specified in NFPA 805, Chapter 
1. In addition, if there are any increases in core damage frequency 
(CDF) or risk as a result of the transition to NFPA 805, the 
increase will be small, governed by the delta risk requirements of 
NFPA 805, and consistent with the intent of the Commission's Safety 
Goal Policy.
    Based on the above, the implementation of the proposed amendment 
to transition the fire protection plan at PNP to one based on NFPA 
805, in accordance with 10 CFR 50.48(c), does not result in a 
significant increase in the probability of any accident previously 
evaluated. In addition, equipment required to mitigate an accident 
remains capable of performing the assumed function.
    Therefore, the consequences of any accident previously evaluated 
are not significantly increased with the implementation of this 
amendment.
    2. Does the proposed amendment create the possibility of a new 
or different kind of accident from any kind of accident previously 
evaluated?
    Response: No.
    Operation of PNP in accordance with the proposed amendment does 
not create the possibility of a new or different kind of accident 
from any accident previously evaluated. Any scenario or previously 
analyzed accident with offsite dose was included in the evaluation 
of DBAs documented in the UFSAR. The proposed change does not alter 
the requirements or function for systems required during accident 
conditions. Implementation of the new fire protection licensing 
basis which complies with the requirements in 10 CFR 50.48(a) and 
(c) and the guidance in RG 1.205, Revision 1 will not result in new 
or different accidents. The proposed amendment does not adversely 
affect accident initiators nor alter design assumptions, conditions, 
or configurations of the facility. The proposed amendment does not 
adversely affect the ability of SSCs to perform their design 
function. SSCs required to safely shut down the reactor and maintain 
it in a safe shutdown condition remain capable of performing their 
design functions.

[[Page 11149]]

    The purpose of this amendment is to permit ENO to adopt a new 
fire protection licensing basis which complies with the requirements 
in 10 CFR 50.48(a) and (c) and the guidance in RG 1.205, Revision 1. 
The NRC considers that NFPA 805 provides an acceptable methodology 
and performance criteria for licensees to identify fire protection 
systems and features that are an acceptable alternative to the 10 
CFR Part 50, Appendix R fire protection features (69 FR 33536; June 
16, 2004).
    The requirements in NFPA 805 address only fire protection and 
the impacts of fire on the plant that have already been evaluated. 
Based on this, the implementation of this amendment does not create 
the possibility of a new or different kind of accident from any kind 
of accident previously evaluated. The proposed changes do not 
involve new failure mechanisms or malfunctions that can initiate a 
new accident.
    Therefore, the possibility of a new or different kind of 
accident from any kind of accident previously evaluated is not 
created with the implementation of this amendment.
    3. Does the proposed amendment involve a significant reduction 
in the margin of safety?
    Response: No.
    Operation of PNP in accordance with the proposed amendment does 
not involve a significant reduction in the margin of safety. The 
proposed amendment does not alter the manner in which safety limits, 
limiting safety system settings or limiting conditions for operation 
are determined. The safety analysis acceptance criteria are not 
affected by this change. The proposed amendment does not adversely 
affect existing plant safety margins or the reliability of equipment 
assumed to mitigate accidents in the UFSAR. The proposed amendment 
does not adversely affect the ability of SSCs to perform their 
design function. SSCs required to safely shut down the reactor and 
to maintain it in a safe shutdown condition remain capable of 
performing their design function.
    The purpose of this amendment is to permit ENO to adopt a new 
fire protection licensing basis which complies with the requirements 
in 10 CFR 50.48(a) and (c) and the guidance in RG 1.205, Revision 1. 
The NRC considers that NFPA 805 provides an acceptable methodology 
and performance criteria for licensees to identify fire protection 
systems and features that are an acceptable alternative to the 10 
CFR Part 50, Appendix R fire protection features (69 FR 33536; June 
16, 2004). Engineering analyses, including engineering evaluations, 
probabilistic safety assessments, and fire modeling calculations, 
have been performed to demonstrate that the performance-based 
methods do not result in a significant reduction in the margin of 
safety.
    Based on this, the implementation of this amendment does not 
significantly reduce the margin of safety. The proposed changes are 
evaluated to ensure that the risk and safety margins are kept within 
acceptable limits.
    Therefore, the transition does not involve a significant 
reduction in the margin of safety.

    The NRC staff has reviewed the licensee's analysis and, based on 
this review, it appears that the three standards of 10 CFR 50.92(c) are 
satisfied. Therefore, the NRC staff proposes to determine that the 
amendment request involves no significant hazards consideration.
    Attorney for licensee: Mr. William Dennis, Assistant General 
Counsel, Entergy Nuclear Operations, Inc., 440 Hamilton Ave., White 
Plains, New York 10601.
    NRC Branch Chief: Robert D. Carlson.

Entergy Nuclear Vermont Yankee, LLC., and Entergy Nuclear Operations, 
Inc., Docket No. 50-271, Vermont Yankee Nuclear Power Station, Vernon, 
Vermont

    Date of amendment request: December 19, 2013. A publicly-available 
version is available in ADAMS under Accession No. ML13358A338.
    Description of amendment request: This amendment request contains 
sensitive unclassified non-safeguards information (SUNSI). The proposed 
amendment would change the Vermont Yankee Cyber Security Plan 
Implementation Schedule Milestone 8 full implementation date from 
December 15, 2014, to June 30, 2016. The proposed amendment would also 
revise the existing operating license Security Plan license condition.
    Basis for proposed no significant hazards consideration 
determination: As required by 10 CFR 50.91(a), the licensee has 
provided its analysis of the issue of no significant hazards 
consideration which is presented below:

    1. Does the proposed change involve a significant increase in 
the probability or consequences of an accident previously evaluated?
    Response: No.
    The proposed change to the CSP [Cyber Security Plan] 
Implementation Schedule is administrative in nature. This change 
does not alter accident analysis assumptions, add any initiators, or 
affect the function of plant systems or the manner in which systems 
are operated, maintained, modified, tested, or inspected. The 
proposed change does not require any plant modifications which 
affect the performance capability of the structures, systems, and 
components relied upon to mitigate the consequences of postulated 
accidents and has no impact on the probability or consequences of an 
accident previously evaluated. Therefore, the proposed change does 
not involve a significant increase in the probability or 
consequences of an accident previously evaluated.
    2. Does the proposed change create the possibility of a new or 
different kind of accident from any accident previously evaluated?
    Response: No.
    The proposed change to the CSP Implementation Schedule is 
administrative in nature. This change does not alter accident 
analysis assumptions, add any initiators, or affect the function of 
plant systems or the manner in which systems are operated, 
maintained, modified, tested, or inspected. The proposed change does 
not require any plant modifications which affect the performance 
capability of the structures, systems, and components relied upon to 
mitigate the consequences of postulated accidents and does not 
create the possibility of a new or different kind of accident 
previously evaluated.
    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.
    Plant safety margins are established through limiting conditions 
for operation, limiting safety system settings, and safety limits 
specified in the Technical Specifications. The proposed change to 
the CSP Implementation Schedule is administrative in nature. In 
addition, the milestone date delay for full implementation of the 
CSP has no substantive impact because other measures have been taken 
which provide adequate protection during this period of time. 
Because there is no change to established safety margins as a result 
of this change, the proposed change does not involve a significant 
reduction in a margin of safety.
    Therefore, the proposed change does not involve a significant 
reduction in a margin of safety.

    The NRC staff has reviewed the licensee's analysis and, based on 
this review, it appears that the three standards of 10 CFR 50.92(c) are 
satisfied. Therefore, the NRC staff proposes to determine that the 
amendment request involves no significant hazards consideration.
    Attorney for licensee: Ms. Jeanne Cho, Assistant General Counsel, 
Entergy Nuclear Operations, Inc., 440 Hamilton Avenue, White Plains, 
New York, 10601.
    NRC Branch Chief: Benjamin G. Beasley.

[[Page 11150]]

Order Imposing Procedures for Access to Sensitive Unclassified Non-
Safeguards Information for Contention Preparation; Arizona Public 
Service Company, et al., Docket Nos. 50-528, 50-529, and 50-530, Palo 
Verde Nuclear Generating Station, Units 1, 2, and 3, Maricopa County, 
Arizona; Duke Energy Carolinas, LLC, Docket Nos. 50-413 and 50-414, 
Catawba Nuclear Station, Units 1 and 2, York County, South Carolina; 
and Docket Nos. 50-369 and 50-370, McGuire Nuclear Station, Units 1 and 
2, Mecklenburg County, North Carolina; Entergy Nuclear Operations, 
Inc., Docket Nos. 50-03, 50-247, and 50-286, Indian Point Nuclear 
Generating, Units 1, 2, and 3, Westchester County, New York; Entergy 
Nuclear Operations, Inc., Docket No. 50-255, Palisades Nuclear Plant, 
Van Buren County, Michigan; Entergy Nuclear Vermont Yankee, LLC. and 
Entergy Nuclear Operations, Inc., Docket No. 50-271, Vermont Yankee 
Nuclear Power Station, Vernon, Vermont

    A. This Order contains instructions regarding how potential parties 
to this proceeding may request access to documents containing 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 such access. 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 requestor 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, 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 Hearing.Docket@nrc.gov and OGCmailcenter@nrc.gov, 
respectively.\1\ The request must include the following information:
---------------------------------------------------------------------------

    \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.
---------------------------------------------------------------------------

    (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 requestor'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.
---------------------------------------------------------------------------

    \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 
the requestor is granted access to that information. However, if more 
than 25 days remain between the date the petitioner is granted 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. 
This provision does not extend the time for filing a request for a 
hearing and petition to intervene, which must comply with the 
requirements of 10 CFR 2.309.
    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 need for access, the NRC staff 
shall immediately notify the requestor in writing, briefly stating the 
reason or reasons for the denial.
    (2) The requestor 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.
    H. Review of Grants of Access. A party other than the requestor 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 with the Chief Administrative Judge 
within 5 days of the notification by the NRC staff of its grant of 
access.
    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\
---------------------------------------------------------------------------

    \3\ Requestors should note that the filing requirements of the 
NRC's E-Filing Rule (72 FR 49139; August 28, 2007), 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

[[Page 11151]]

standing and who have propounded contentions meeting the specificity 
and basis requirements in 10 CFR Part 2. Attachment 1 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 21st day of February 2014.

    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....................  Nuclear Regulatory Commission (NRC) staff
                         informs the requestor 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 requestor/
                         petitioner 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 hearing or opportunity for hearing), 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.
------------------------------------------------------------------------


[FR Doc. 2014-04302 Filed 2-26-14; 8:45 am]
BILLING CODE 7590-01-P