[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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