[Federal Register Volume 70, Number 204 (Monday, October 24, 2005)]
[Notices]
[Pages 61475-61477]
From the Federal Register Online via the Government Publishing Office [www.gpo.gov]
[FR Doc No: E5-5854]
=======================================================================
-----------------------------------------------------------------------
NUCLEAR REGULATORY COMMISSION
[Docket No. 50-387]
Susquehanna Steam Electric Station, Unit 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.
NPF-14 and NPF-22, issued to PPL Susquehanna, LLC (PPL, the licensee),
for operation of the Susquehanna Steam Electric Station, Unit 1 (SSES
1), located in Berwick, Pennsylvania.
The proposed amendment would revise the SSES 1 Technical
Specification (TS) Section 2.1.1.2 with regard to the Unit 1 Cycle 14
(U1C14) minimum critical power ratio (MCPR) safety limit (SL) for two-
loop operation from 1.08 to 1.09 following implementation of a
redesigned core. The change to the MCPR SL is necessary due to control
cell friction issues which necessitate a U1C14 mid-cycle core redesign
and unit shutdown to implement.
The exigent amendment request is being made following PPL's
determination, based in part, on testing performed the weekend of
September 30, 2005, that a mid-cycle core redesign was the most prudent
course of action to ensure safe, reliable operation for the remainder
of U1C14. Additionally, PPL requests the proposed change on an exigent
basis to avoid unnecesary delays in the Unit 1 restart following its
upcoming maintenance outage.
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.
Pursuant to 10 CFR 50.91(a)(6) for amendments to be granted under
exigent circumstances, the NRC staff must determine that the amendment
request involves 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. 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 MCPR Safety Limits does not directly
or indirectly affect any plant system, equipment, component, or
change the processes used to operate the plant. Further, the revised
U1C14 MCPR Safety Limits are generated using NRC approved
methodology and meet the applicable acceptance criteria. In
addition, the effects of channel bow were conservatively addressed
by increasing the amount of channel bow assumed in the MCPR SL
calculation. Thus, this proposed amendment does not involve a
significant increase in the probability or consequences of an
accident previously evaluated.
Prior to the restart of U1C14, licensing analyses will be
performed on the redesigned core (using NRC approved methodology
referenced in Technical Specification Section 5.6.5.b) to determine
changes in the critical power ratio as a result of anticipated
operation occurrences. These results will be added to the MCPR
Safety Limit values proposed herein to generate the MCPR operating
limits in the U1C14 Core Operating Limits Report (COLR). The COLR
operating limits thus assure that the MCPR Safety Limit will not be
exceeded during normal operation or anticipated operational
occurrences. Postulated accidents are also analyzed to confirm NRC
acceptance criteria are met.
Therefore, this proposed amendment 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.
This proposed change to the MCPR Safety Limits does not directly
or indirectly affect any plant system, equipment, or component and
therefore they do not affect the failure modes of any of these
items. Thus, the proposed change does not create the possibility of
a previously unevaluated operator error or a new single failure.
Therefore, this proposed amendment does not create the
possibility of a new or different kind of accident from any
previously evaluated.
3. Does the proposed change involve a significant reduction in a
margin of safety?
Response: No.
Since the proposed change does not alter any plant system,
equipment, component, or the processes used to operate the plant,
the proposed change will not jeopardize or degrade the function or
operation of any plant system or component governed by Technical
Specifications. The proposed MCPR Safety Limits do not involve a
significant reduction in the margin of safety as currently defined
in the Bases of the applicable Technical Specification sections,
because the MCPR Safety Limits calculated for the remaining U1C14
operation preserve the required 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.
The Commission is seeking public comments on this proposed
determination. Any comments received within 14 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 the 14-day notice period. However, should circumstances
change during the notice period, such that failure to act in a timely
way would result, for example, in derating or shutdown of the facility,
the Commission may issue the license amendment before the expiration of
the 14-day notice period, provided that its final determination is that
the amendment involves no significant hazards consideration. The final
determination will consider all public and State comments received.
Should the Commission take this action, it will publish in the Federal
Register a notice of 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, Rules and
Directives Branch, 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 delivered to
Room 6D59, Two White Flint North, 11545 Rockville Pike, Rockville,
Maryland, from 7:30
[[Page 61476]]
a.m. to 4:15 p.m. Federal workdays. Documents may be examined, and/or
copied for a fee, at the NRC's Public Document Room, located at One
White Flint North, 11555 Rockville Pike (first floor), Rockville,
Maryland.
The filing of requests for hearing and petitions for leave to
intervene is discussed below.
Within 60 days after the date of publication of this notice, the
licensee may file a request for a hearing with respect to issuance of
the amendment to the subject facility operating license and any person
whose interest may be affected by this proceeding and who wishes to
participate as a party in the proceeding must file a written request
for a hearing and a petition for leave to intervene. 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 persons 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
01F21, 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/requestor is aware and on
which the petitioner/requestor intends to rely to establish those facts
or expert opinion. The petitioner/requestor must provide 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/
requestor 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.
Nontimely requests and/or petitions and contentions will not be
entertained absent a determination by the Commission or the presiding
officer of the Atomic Safety and Licensing Board that the petition,
request and/or the contentions should be granted based on a balancing
of the factors specified in 10 CFR 2.309(c)(1)(i)-(viii).
A request for a hearing or a petition for leave to intervene must
be filed 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; (2) courier, express mail, and expedited delivery services:
Office of the Secretary, Sixteenth Floor, One White Flint North, 11555
Rockville Pike, Rockville, Maryland 20852, Attention: Rulemaking and
Adjudications Staff; (3) E-mail addressed to the Office of the
Secretary, U.S. Nuclear Regulatory Commission, [email protected];
or (4) facsimile transmission addressed to the Office of the Secretary,
U.S. Nuclear Regulatory Commission, Washington, DC, Attention:
Rulemakings and Adjudications Staff at (301) 415-1101, verification
number is (301) 415-1966. A copy of the request for hearing and
petition for leave to intervene should also be sent to the Office of
the General Counsel, U.S. Nuclear Regulatory Commission, Washington, DC
20555-0001, and it is requested that copies be transmitted either by
means of facsimile transmission to 301-415-3725 or by e-mail to
[email protected]. A copy of the request for hearing and petition
for leave to intervene should also be sent to Bryan A. Snapp, Esquire,
Assoc. General Counsel, PPL Services Corporation, 2 North Ninth St.,
GENTW3, Allentown, PA 18101-1179, attorney for the licensee.
For further details with respect to this action, see the
application for amendment dated October 14, 2005, which is available
for public inspection at the Commission's Public Document Room (PDR),
located at One White Flint North, Public File Area O1 F21, 11555
Rockville Pike (first floor), Rockville, Maryland. Publicly available
records will be accessible electronically 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.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 [email protected].
Dated at Rockville, Maryland, this 17th day of October 2005.
[[Page 61477]]
For the Nuclear Regulatory Commission.
Richard J. Laufer,
Section Chief, Section 1, Project Directorate I, Division of Licensing
Project Management, Office of Nuclear Reactor Regulation.
[FR Doc. E5-5854 Filed 10-21-05; 8:45 am]
BILLING CODE 7590-01-P