[Federal Register Volume 72, Number 141 (Tuesday, July 24, 2007)]
[Notices]
[Pages 40342-40344]
From the Federal Register Online via the Government Publishing Office [www.gpo.gov]
[FR Doc No: E7-14250]
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NUCLEAR REGULATORY COMMISSION
[Docket Nos. 50-277 and 50-278]
Exelon Generation Company, LLC, and PSEG Nuclear, LLC; Notice of
Consideration of Issuance of Amendments to Renewed Facility Operating
Licenses, 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 Renewed Facility Operating
License Nos. DPR-44 and DPR-56 issued to Exelon Generation Company,
LLC, and PSEG Nuclear, LLC (the licensees), for operation of the Peach
Bottom Atomic Power Station (PBAPS), Units 2 and 3 located in York and
Lancaster Counties, Pennsylvania.
The proposed amendment would modify the main steam isolation valve
(MSIV) leakage Technical Specification (TS) Surveillance Requirement
(SR) 3.6.1.3.14 to establish a total leakage rate limit for the sum of
the four main steam lines.
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), Part 50, 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 results in no change in radiological
consequences of the design basis LOCA as currently analyzed for
Peach Bottom Atomic Power Station [PBAPS]. This analysis was
calculated assuming a combined total MSlV leakage at accident
pressure for determining acceptance to the regulatory limits for the
offsite, control room and Technical Support Center (TSC) radiation
doses as contained in 10 CFR Part 100 and 10 CFR Part 50, Appendix
A, GDC 19. The proposed change does not compromise existing
radiological equipment qualification, since the combined total MSlV
leakage rate has been factored into existing equipment qualification
analyses for 10 CFR 50.49. This change will not alter the operation
of process variables, structures, systems, or components as
described in the PBAPS Updated Final Safety Analysis Report (UFSAR).
The proposed amendment does not alter the operational capability of
the MSIVs.
Therefore, based on the above information, 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?
[[Page 40343]]
Response: No.
The proposed amendment does not modify the MSlVs or any other
plant system or structure associated with this amendment and
therefore, will not affect their capability to perform their design
functions. The combined total main steam line leakage rate is
included in the current radiological analyses for the assessment of
radiation exposure following an accident. This proposal changes the
allowable leakage rate from a per valve limit to a total combined
leakage rate limit for all four main steam lines, but does not
change the cumulative limit. The proposed change does not affect the
responses of plant equipment to transient or accident conditions.
The proposed amendment does not change or introduce any new
equipment, modes of system operation or failure mechanisms.
Therefore, based on the above information, the proposed
amendment does not create the possibility of a new or different kind
of accident from any previously evaluated.
3. Does the proposed amendment involve a significant reduction
in a margin of safety?
Response: No.
The proposed amendment has no impact on equipment design or
operation, and there are no changes being made to safety limits or
safety system allowable values that would adversely affect plant
safety. The proposed change does not affect safety analysis
assumptions or initial conditions and therefore, the margin of
safety in the original safety analyses are maintained. The leakage
rate limit specified for the MSlVs is used to quantify the maximum
amount of bypass leakage assumed in the LOCA radiological analysis.
Results of the analysis are evaluated against the dose guidelines
contained in 10 CFR Part 100 and 10 CFR Part 50, Appendix A, GDC 19.
The margin of safety in this context is considered to be the
difference between the calculated dose exposures and the guidelines
provided by 10 CFR Part 100 and GDC 19. Therefore, since the
proposed combined total main steam line leakage rate limit is
unchanged from the assumed maximum leakage rate for MSlVs for the
purpose of calculating potential radiation dose, the margin of
safety is not affected.
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
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,
Directives and Editing 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 (PDR), located at One White Flint North, Public File Area
O1 F21, 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
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 requestors/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.
[[Page 40344]]
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 General Counsel, Exelon Generation Company, LLC, 4300
Winfield Road, Warrenville, IL 60555, attorney for the licensee.
For further details with respect to this action, see the
application for amendment dated March 6, 2007, which is available for
public inspection at the Commission's 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 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/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 [email protected].
Dated at Rockville, Maryland, this 17th day of July 2007.
For the Nuclear Regulatory Commission.
John Hughey,
Project Manager, Plant Licensing Branch 1-2, Division of Operating
Reactor Licensing, Office of Nuclear Reactor Regulation.
[FR Doc. E7-14250 Filed 7-23-07; 8:45 am]
BILLING CODE 7590-01-P