[Federal Register Volume 74, Number 197 (Wednesday, October 14, 2009)]
[Notices]
[Pages 52824-52826]
From the Federal Register Online via the Government Publishing Office [www.gpo.gov]
[FR Doc No: E9-24721]


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NUCLEAR REGULATORY COMMISSION

[NRC-2009-0451; Docket No. 50-220]


Nine Mile Point Nuclear Station, Unit No. 1; Notice of 
Consideration of Issuance of Amendment to Facility Operating License, 
Proposed No Significant Hazards Consideration Determination, and 
Opportunity for a Hearing

    The U.S. Nuclear Regulatory Commission (the Commission) is 
considering issuance of an amendment to Facility Operating License No. 
DPR-63 issued to Nine Mile Point Nuclear Station, LLC (the licensee) 
for operation of Nine Mile Point, Unit No. 1 (NMP1) located in Oswego, 
NY.
    The proposed amendment would modify Technical Specification (TS) 
sections 3.2.7.1 and 4.2.7.1, ``Primary Coolant System Pressure 
Isolation Valves,'' to incorporate requirements that are consistent 
with section 3.4.5 of the Improved Standard TSs, NUREG-1433, Revision 
3. The proposed TS changes include the addition of applicable reactor 
operating conditions, addition of actions to be taken when pressure 
isolation valve (PIV) leakage is not within limit, relocation of the 
PIV leakage limit criterion from TS Table 3.2.7.1 to Specification 
4.2.7.1.a, replacement of the existing PIV leakage test frequencies 
with a reference to the Inservice Testing Program, and deletion of TS 
Table 3.2.7.1, ``Primary Coolant System Pressure Isolation Valves.'' 
The list of PIVs would be relocated from TS Table 3.2.7.1 to the NMP1 
Updated Final Safety Analysis Report, consistent with the guidance in 
Generic Letter (GL) 91-08, ``Removal of Component Lists from Technical 
Specifications.''
    Before issuance of the proposed license amendment, the Commission 
will have made findings required by the Atomic Energy Act of 1954, as 
amended (the Act), and the Commission's regulations.
    The Commission has made a proposed determination that the amendment 
request involves no significant hazards consideration. Under the 
Commission's regulations in Title 10 of the Code of Federal Regulations 
(10 CFR), section 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. As required 
by 10 CFR 50.91(a), the licensee has provided its analysis of the issue 
of no significant hazards consideration, which is presented below:

    1. Does the proposed amendment involve a significant increase in 
the probability or consequences of an accident previously evaluated?
    Response: No.
    The proposed amendment involves changes to the TS requirements 
that apply to reactor coolant system (RCS) PIVs. No physical plant 
changes are involved. PIVs isolate the boundary between the high 
pressure RCS and connected low pressure piping systems. The TS 
requirements are intended to detect PIV degradation that has the 
potential to cause a loss of coolant accident (LOCA) outside of 
containment due to the failure of low pressure portions of systems 
connected to the RCS.
    The proposed changes to the TS requirements are consistent with 
NUREG-1433, ``Standard Technical Specifications, General Electric 
Plants, BWR/4,'' and will continue to ensure that excessive leakage 
through these valves is properly identified and resolved. Testing in 
accordance with the IST [Inservice Testing] Program will continue to 
detect PIV leakage in excess of the established limits, which are 
not being changed. When these limits are exceeded, required actions 
will initiate appropriate activities to minimize the impact of the 
leakage. These actions will not adversely impact nuclear safety 
because the flow paths will be sufficiently isolated, the period of 
time without redundant isolation capability will be appropriately 
limited, and the probability of a second valve failing during this 
time period is low. Thus, the proposed amendment does not result in 
operation that would make an accident more likely to occur, and does 
not alter assumptions relative to mitigation of a previously 
evaluated accident.
    Relocation of the list of PIVs from the TS to a licensee-
controlled document (the UFSAR) in accordance with the guidance in 
GL 91-08 is an administrative change that does not alter the TS 
requirements that are applicable to the PIVs. Based on the above 
discussion, it is concluded that the proposed amendment does not 
involve a significant increase in the probability or consequences of 
an accident previously evaluated.
    2. Does the proposed amendment create the possibility of a new 
or different kind of accident from any accident previously 
evaluated?
    Response: No.
    The proposed amendment involves changes to the TS requirements 
that apply to RCS PIVs. These changes to the TS requirements are 
consistent with NUREG-1433. The proposed changes do not involve a 
physical alteration of the plant (no new or different type of 
equipment will be installed) or changes in the methods governing 
normal plant operation. The changes also do not alter the design 
function of the PIVs and do not adversely affect the ability of the 
PIVs to perform their design function.
    Therefore, the proposed amendment does not create the 
possibility of a new or different kind of accident from any accident 
previously evaluated.
    3. Does the proposed amendment involve a significant reduction 
in a margin of safety?
    Response: No.
    The proposed amendment involves changes to the TS requirements 
that apply to RCS PIVs. No physical plant changes are involved. PIVs 
isolate the boundary between the high pressure RCS and connected low 
pressure piping systems. The revised TS PIV requirements will 
continue to ensure that excessive leakage through these valves is 
properly identified and resolved, such that a LOCA outside of 
containment due to the failure of low pressure portions of systems 
connected to the RCS will be no more likely to occur. Thus, the 
proposed amendment will not result in a design basis or safety limit 
being exceeded or altered.
    Based on the above discussion, it is concluded that 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.
    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

[[Page 52825]]

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.
    Written comments may be submitted by mail to the Chief, Rulemaking 
and Directives Branch (RDB), TWB-05-B01M, Division of Administrative 
Services, Office of Administration, U.S. Nuclear Regulatory Commission, 
Washington, DC 20555-0001, and should cite the publication date and 
page number of this Federal Register notice. Written comments may also 
be faxed to the RDB at 301-492-3446. Documents may be examined, and/or 
copied for a fee, at the NRC's Public Document Room (PDR), located at 
One White Flint North, Public File Area O1 F21, 11555 Rockville Pike 
(first floor), Rockville, Maryland.
    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. 
Requests for a hearing and a petition for leave to intervene shall be 
filed in accordance with the Commission's ``Rules of Practice for 
Domestic Licensing Proceedings'' in 10 CFR part 2. Interested person(s) 
should consult a current copy of 10 CFR 2.309, which is available at 
the Commission's PDR, located at One White Flint North, Public File 
Area O1F21, 11555 Rockville Pike (first floor), Rockville, Maryland. 
Publicly available records will be accessible from the Agencywide 
Documents Access and Management System's (ADAMS) Public Electronic 
Reading Room on the Internet at the NRC Web site, http://www.nrc.gov/reading-rm/doc-collections/cfr/. If a request for a hearing or petition 
for leave to intervene is filed by the above date, 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 identify the specific contentions which the petitioner/requestor 
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 
petitioner/requestor 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 petitioner 
intends to rely in proving the contention at the hearing. The 
petitioner/requestor must also provide references to those specific 
sources and documents of which the petitioner is aware and on which the 
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 petitioner to relief. A petitioner/requestor 
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, 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, 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 E-Filing rule, which the NRC 
promulgated in August 28, 2007 (72 FR 49139). 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 
ten (10) days prior to the filing deadline, the petitioner/requestor 
must contact the Office of the Secretary by e-mail at 
<a href="/cdn-cgi/l/email-protection#38505d594a51565f165c575b535d4c78564a5b165f574e"><span class="__cf_email__" data-cfemail="d4bcb1b5a6bdbab3fab0bbb7bfb1a094baa6b7fab3bba2">[email protected]</span></a>, or by calling (301) 415-1677, to request (1) A 
digital 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/or (2) 
creation of an electronic docket for the proceeding (even in instances 
in which the petitioner/requestor (or its counsel or representative) 
already holds an NRC-issued digital ID certificate). Each petitioner/
requestor will need to download the Workplace Forms Viewer\TM\ to 
access the Electronic Information Exchange (EIE), a component of the E-
Filing system. The Workplace Forms ViewerJ is free and is available at 
http://www.nrc.gov/site-help/e-submittals/install-viewer.html.

[[Page 52826]]

Information about applying for a digital ID certificate is available on 
NRC's public Web site at http://www.nrc.gov/site-help/e-submittals/apply-certificates.html.
    Once a petitioner/requestor has obtained a digital ID certificate, 
had a docket created, and downloaded the EIE viewer, it can then submit 
a request for hearing or petition for leave to intervene. Submissions 
should be in Portable Document Format (PDF) in accordance with NRC 
guidance available on the NRC public Web site at http://www.nrc.gov/site-help/e-submittals.html. A filing is considered complete at the 
time the filer submits its documents through EIE. To be timely, an 
electronic filing must be submitted to the EIE 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 e-mail notice confirming receipt of the document. The 
EIE system also distributes an e-mail notice that provides access to 
the document to the NRC 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 through the ``Contact Us'' link 
located on the NRC Web site at http://www.nrc.gov/site-help/e-submittals.html or by calling the NRC Meta-System Help Desk, which is 
available between 8 a.m. and 8 p.m., Eastern Time, Monday through 
Friday, excluding government holidays. The Meta-System Help Desk can be 
contacted by telephone at 1-866-672-7640 or by e-mail at 
<a href="/cdn-cgi/l/email-protection#367b657e721864534559434455537658445518515940"><span class="__cf_email__" data-cfemail="0c415f4448225e697f63797e6f694c627e6f226b637a">[email protected]</span></a>.
    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.
    Non-timely requests and/or petitions and contentions will not be 
entertained absent a determination by the Commission, the presiding 
officer, or the Atomic Safety and Licensing Board that the request and/
or petition should be granted and/or the contentions should be 
admitted, based on a balancing of the factors specified in 10 CFR 
2.309(c)(1)(i)-(viii).
    Documents submitted in adjudicatory proceedings will appear in 
NRC's electronic hearing docket which is available to the public at 
http://ehd.nrc.gov/ehd_proceeding/home.asp, unless excluded pursuant 
to an order of the Commission, an Atomic Safety and Licensing Board, or 
a 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. 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 submissions.
    For further details with respect to this license amendment 
application, see the application for amendment dated September 18, 2009 
(Agencywide Documents Access and Management System (ADAMS) Accession 
No. ML092640681), which is available for public inspection at the 
Commission's PDR, located at One White Flint North, File Public Area O1 
F21, 11555 Rockville Pike (first floor), Rockville, Maryland. Publicly 
available records will be accessible electronically from the ADAMS 
Public Electronic Reading Room on the Internet at the NRC Web site, 
http://www.nrc.gov/reading-rm/adams.html. Persons who do not have 
access to ADAMS or who encounter problems in accessing the documents 
located in ADAMS, should contact the NRC PDR Reference staff by 
telephone at 1-800-397-4209, 301-415-4737, or by e-mail to 
<a href="/cdn-cgi/l/email-protection#ff8f9b8dd18d9a8c908a8d9c9abf918d9cd1989089"><span class="__cf_email__" data-cfemail="5c2c382e722e392f33292e3f391c322e3f723b332a">[email protected]</span></a>.
    Attorney for licensee: Mark J. Wetterhahn, Esquire, Winston & 
Strawn, 1700 K Street, NW., Washington, DC 20006.

    Dated at Rockville, Maryland, this 6th day of October 2009.
    For the Nuclear Regulatory Commission.

Richard V. Guzman,
Senior Project Manager, Plant Licensing Branch 1-1, Division of 
Operating Reactor Licensing, Office of Nuclear Reactor Regulation.
[FR Doc. E9-24721 Filed 10-13-09; 8:45 am]
BILLING CODE 7590-01-P


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