[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