[Federal Register Volume 69, Number 53 (Thursday, March 18, 2004)]
[Notices]
[Pages 12873-12874]
From the Federal Register Online via the Government Publishing Office [www.gpo.gov]
[FR Doc No: 04-6081]


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NUCLEAR REGULATORY COMMISSION


Biweekly Notice; Applications and Amendments Facility Operating 
Licenses Involving No Significant Hazards Considerations; Correction

AGENCY: Nuclear Regulatory Commission.

ACTION: Notice of issuance; correction.

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SUMMARY: This document corrects an entry in the biweekly notice 
appearing in the Federal Register on January 20, 2004 (69 FR 2735). The 
corrected information considers issuance of an amendment to Facility 
Operating License No. NPF-16, issued to Florida Power and Light 
Company, St. Lucie Plant, Unit No. 2 (Docket No. 50-389). This action 
is necessary to include text that was missing. This notice is being 
republished in its entirety.

FOR FURTHER INFORMATION CONTACT: Beverly A. Clayton, Office of Nuclear 
Reactor Regulation, Nuclear Regulatory Commission, Washington, DC 
20555-0001, telephone: 301-415-3475, e-mail: [email protected].

SUPPLEMENTARY INFORMATION: On page 2743, near the bottom of the second 
column the notice starting with ``Florida Power and Light,'' and ending 
in the third column with ``NRC Section Chief: Allen G. Howe,'' should 
read as follows:

Florida Power and Light Company, Docket No. 50-389, St. Lucie Plant, 
Unit No. 2, St. Lucie County, Florida

    Date of amendment request: December 2, 2003.
    Description of amendment request: The proposed amendment would 
revise the Technical Specifications to allow a reduction in the minimum 
reactor coolant system flow, corresponding to an increase in the steam 
generator tube plugging limit from 15 percent to 30 percent.
    Basis for proposed no significant hazards consideration 
determination: 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) Operation of the facility in accordance with the proposed 
amendment would not involve a significant increase in the 
probability or consequences of an accident previously evaluated.
    None of the proposed changes to the Technical Specifications nor 
the reload methodology result in operation of the facility that 
would adversely affect the initiation of any accident previously 
evaluated. There is no adverse impact on any plant system. All 
systems will function as designed, and all performance requirements 
for these systems remain acceptable. The comprehensive engineering 
effort, performed to support the proposed changes, has included 
evaluations or analyses of all the accident analyses including the 
effects of ZIRLOTM fuel rod cladding. The DNBR and 
setpoint analyses have verified that the accident analyses criteria 
continue to be met.
    Dose consequences acceptance criteria have been verified to be 
met for all the events.
    Therefore, the proposed changes do not significantly increase 
the probability or consequences of an accident previously evaluated.
    (2) Operation of the facility in accordance with the proposed 
amendments would not create the possibility of a new or different 
kind of accident from any previously evaluated.
    No new accident scenarios, failure mechanisms or limiting single 
failures are introduced as a result of the proposed changes to the 
Technical Specifications and the reload methodology. The proposed 
changes have no adverse effects on any safety-related systems and do 
not challenge the performance or integrity of any safety-related 
system. The DNBR limits and trip setpoints associated with the 
respective reactor protection system functions have verified that 
the accident analyses criteria continue to be met.
    Therefore, this amendment will not create the possibility of a 
new or different kind of accident from any accident previously 
evaluated.
    (3) Operation of the facility in accordance with the proposed 
amendments would not involve a significant reduction in a margin of 
safety.
    The safety analyses of all design basis accidents, supporting 
the proposed changes to the Technical Specifications and the reload 
methodology, continue to meet the applicable acceptance criteria 
with respect to the radiological consequences, specified acceptable 
fuel design limits (SAFDLs), primary and secondary 
overpressurization, and 10 CFR 50.46 requirements. The DNBR and the 
setpoint analyses are performed on a cycle-specific basis to verify 
that the reactor protection system functions continue to provide 
adequate protection against fuel design limits. Revised steam line 
break and LOCA mass and energy releases were determined and used to 
confirm the overall containment response remains acceptable. The 
performance requirements for all systems have been verified to be 
acceptable from design basis accidents' consideration. The proposed 
amendment, therefore, will not involve a significant reduction in 
the margin of safety.


[[Page 12874]]


    The NRC staff has reviewed the licensee's analysis and, based on 
this review, it appears that the three standards of Sec.  50.92(c) are 
satisfied. Therefore, the NRC staff proposes to determine that the 
amendment request involves no significant hazards consideration.
    Attorney for licensee: M.S. Ross, Attorney, Florida Power & Light, 
P.O. Box 14000, Juno Beach, Florida 33408-0420.
    NRC Section Chief: Allen G. Howe.

    Dated in Rockville, Maryland, this 12th day of March, 2004.

    For the U.S. Nuclear Regulatory Commission.
Michael T. Lesar,
Chief, Rules and Directives Branch, Division of Administrative 
Services, Office of Administration.
[FR Doc. 04-6081 Filed 3-17-04; 8:45 am]
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