[Federal Register Volume 71, Number 118 (Tuesday, June 20, 2006)]
[Notices]
[Pages 35453-35456]
From the Federal Register Online via the Government Publishing Office [www.gpo.gov]
[FR Doc No: E6-9629]
-----------------------------------------------------------------------
NUCLEAR REGULATORY COMMISSION
[Docket No. 50-353]
Limerick Generating Station, Unit 2; 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-85, issued to Exelon Generation Company, LLC, for operation of the
Limerick Generating Station, Unit 2, located in Montgomery County,
Pennsylvania.
The proposed one-time amendment would revise Technical
Specification (TS) Limiting Condition for Operation (LCO) 3.6.1.7
concerning drywell average air temperature. Specifically,
[[Page 35454]]
the proposed change would add a footnote to the TS limit for drywell
average air temperature of 145 degrees Fahrenheit ([deg]F) to allow
continued operation of LGS, Unit 2, with drywell average air
temperature no greater than 148 [deg]F or the remainder of the current
operating cycle (Cycle 9), which is currently scheduled to end in March
2007, or until the next shutdown of sufficient duration to allow for
unit cooler fan repairs, whichever comes first.
The exigent amendment request is being made because both fans of
the 2D drywell unit cooler are inoperable and out of service, which
resulted in an increase in drywell average air temperature from
approximately 129 [deg]F to approximately 142 [deg]F. Historically, LGS
has experienced an increase in the drywell average air temperature of
2-4 [deg]F during the summer months with normal drywell air cooling
system operation. Under the current plant condition, this could result
in the potential to exceed the TS limit of 145 [deg]F. Noticing this
license amendment request in the Biweekly Federal Register Notice for
the standard 30-day public comment period would not expire until July
2006. Therefore, the combination of the increase in the drywell average
air temperature during the summer months and the standard regulatory
process for noticing license amendment requests could result in an
unwarranted plant shutdown.
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 increase in the allowable drywell average air
temperature during normal plant operation does not make any physical
changes to the plant. It only permits the plant to operate at a
higher drywell average air temperature for a limited period of time,
and therefore, does not increase the probability of an accident
previously evaluated. This increase in the drywell average air
temperature has been evaluated to ensure that the change does not
adversely affect the ability of the primary containment to perform
its safety related function during accident conditions.
The LGS containment design was previously evaluated using an
initial average air temperature of 150 [deg]F for the design basis
Loss-of-Coolant Accident (LOCA). The results of this evaluation
showed that the peak drywell air temperature does not exceed the
limit of 340 [deg]F post-accident and that the peak drywell pressure
does not exceed the design limit of 55 psig. In addition, the
results of this evaluation showed that the peak suppression pool
temperature does not exceed the suppression pool structural design
limit of 220 [deg]F, and does not exceed the low pressure Emergency
Core Cooling System (ECCS) pump net positive suction head (NPSH)
limit of 212 [deg]F. The proposed change is also bounded by the
current small line break analysis.
Evaluation of components in the drywell has determined that the
proposed one-time increase in the drywell average air temperature
does not adversely affect the capability to perform their safety
function. For components in the drywell, the qualified life was
based on operation at a minimum drywell average air temperature of
145 [deg]F. An evaluation of the qualified life of components in the
drywell has been performed and has determined that current
qualification will not be adversely impacted even if the components
are exposed to a temperature of 150 [deg]F for the remainder of the
current operating cycle. The increased average air temperature of
the drywell atmosphere does not degrade or compromise any coolant
boundaries nor does it degrade or compromise any primary containment
boundaries from performing their design functions during or
following an accident condition. This proposed change does not
result in or require any systems or components to be operated
outside of their design limits.
This proposed change does not adversely affect mitigating
systems, structures or components, and does not adversely affect the
initial conditions of any accidents. Redundancy and diversity of
mitigating systems are unchanged as a result of this proposed
change. This proposed change does not affect onsite or offsite
radiological consequences of any accident previously evaluated in
the Safety Analysis Report (SAR).
Therefore, this proposed TS 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 one-time increase in the drywell average air
temperature proposed by this TS change does not change any SSC
[structures, systems, and components of the plant. This TS change
does not create new operating or failure modes. The normal operating
drywell average air temperature is maintained to prevent the peak
temperature/pressure of the primary containment from exceeding the
design limit, and to ensure that SSCs perform their safety functions
before, during and after accident conditions. A previous evaluation
has shown that the limits for the drywell and suppression pool
design temperatures and pressures are not exceeded by the proposed
change.
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. This proposed change will allow the plant to
operate at a higher drywell average air temperature during normal
operation for the remainder of the current operating cycle. This
higher drywell average air temperature (148 [deg]F) is still below
the initial conditions (150 [deg]F) specified in the current short
and long-term containment analyses. This change does not create
additional heat loads or change the way any of the equipment is
operated. A previous evaluation has demonstrated that the drywell
and suppression pool design pressures and design temperatures and
code requirements are maintained. Therefore, this one-time change to
the TS drywell average air temperature limit, to allow the plant to
operate no greater than 148 [deg]F for no longer than the remainder
of the current operating cycle, does not have any adverse effect on
the ability of safety-related SSCs to perform their design
functions. The SSCs are designed to function following a LOCA where
drywell temperature can peak at 340 [deg]F. For components in the
drywell, the qualified life was based on operation at a minimum
drywell average air temperature of 145 [deg]F. An evaluation of the
qualified life of components in the drywell has been performed and
has determined that current qualification will not be adversely
impacted even if the components are exposed to a temperature of 150
[deg]F for the remainder of the current operating cycle.
Therefore, this 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.
[[Page 35455]]
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 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 Mr. Brad Fewell,
Assistant
[[Page 35456]]
General Counsel, Exelon Generation Company, LLC, 200 Exelon Way,
Kennett Square, PA 19348, attorney for the licensee.
For further details with respect to this action, see the
application for amendment dated June 9, 2006, 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 14th day of June 2006.
For the Nuclear Regulatory Commission.
Richard V. Guzman,
Project Manager, Plant Licensing Branch I-2, Division of Operating
Reactor Licensing, Office of Nuclear Reactor Regulation.
[FR Doc. E6-9629 Filed 6-19-06; 8:45 am]
BILLING CODE 7590-01-P