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License Amendment Request for Extended Power Uprate, Attachment 4; Technical Specifications Bases Markups
	ML103560428
Person / Time
Site:	Saint Lucie
Issue date:	12/15/2010
From:	; Florida Power & Light Co
To:	; Office of Nuclear Reactor Regulation
References
	L-2010-259
	Download: ML103560428 (25)
	v • d • e

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The trip setpoint and the methodology used to determine the trip setpoint, the as-found acceptance criteria band, and the as-left acceptance criteria are specified in the UFSAR. The two footnotes on the bottom of TS Table 2.2-1 are consistent with the two recommended notes provided in NRC's letter to the NEI Technical Setpoint Methods Task Force for Setpoint Allowables dated September 7, 2005.

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and 10 CFR 50.67 (Ref. 7).

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The maximum allowable doses to an individual at the exclusion area boundary (EAB) distance for 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months following an accident, or at the low population zone (LPZ) outer boundary distance for the radiological release duration, are specified in 10 CFR 50.67 for design basis accidents using the alternative source term methodology and in Branch Technical Position 11-5 for the waste gas decay tank rupture accident. Dose limits to control room operators are given in 10 CFR 50.67 and in GDC 19.

The RCS specific activity LCO limits the allowable concentration of radionuclides in the reactor coolant to ensure that the dose consequences of limiting accidents do not exceed appropriate regulatory offsite and control room dose acceptance criteria. The LCO contains specific activity limits for both DOSE EQUIVALENT (DE) I-131 and DOSE EQUIVALENT (DE) XE-133.

The radiological dose assessments assume the specific activity of the reactor coolant is at the LCO limits, and an existing reactor coolant steam generator tube leakage rate at the applicable Technical specification limit. The radiological dose assessments assume the specific activity of the secondary coolant is at its limit as specified in LCO 3.7.1.4, Plant Systems - Activity.

The ACTIONS allow operation when DOSE EQUIVALENT I-131 is greater than 1.0 Ci/gram and less than 60 Ci/gram. The ACTIONS require sampling within four hours and every four hours following to establish a trend.

One surveillance requires the determination of the DE XE-133 specific activity as a measure of noble gas specific activity of the reactor coolant at least once per 7 days.

A second surveillance is performed to ensure that iodine specific activity remains within the LCO limit once per 14 days during normal operation and following rapid power changes when iodine spiking is more apt to occur. The frequency between two and six hours after a power change of greater than 15% RATED THERMAL POWER within a 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months period, is established because the iodine levels peak during this time following iodine spike initiation.

The RCS specific activity satisfies Criterion 2 of 10 CFR 50.36(c)(2)(ii).

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Branch Technical Position 11-5, "Postulated Radioactive Releases Due to Waste Gas System Leak or Failure," of Standard Review Plan Chapter 11, Radioactive Waste Management," of NUREG-0800.

The waste gas decay tank inventory source term required to generate an exclusion area boundary dose of 0.1 rem is the basis for the limit of 202,500 dose equivalent curies Xe-133, and is derived based on the definition given in Technical Specification Task Force (TSTF)-490, Deletion of E Bar Definition and Revision to RCS Specific Activity Tech Spec.

ML103560428

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