ML103560428

St. Lucie, Unit 1 - 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)

Text

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Thetripsetpointandthemethodologyusedtodeterminethetrip setpoint,theas-foundacceptancecriteriaband,andtheas-left acceptancecriteriaarespecifiedintheUFSAR.Thetwofootnoteson thebottomofTSTable2.2-1areconsistentwiththetworecommended notesprovidedinNRC'slettertotheNEITechnicalSetpointMethods TaskForceforSetpointAllowablesdatedSeptember7,2005.

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1. 1. 1. 1. TheElimitsEareEcycleJspecificEandEhaveEbeen relocatedEtoEtheEFOLRH 0/activityinthedtwosources:1),and2)thepre-existingsecondarysidefluidinventory,"andthesecondarycoolantsystemactivityisassumedtobeequaltothelimitsinLCO3.7.1.4,"PlantSystemsActivity."and10CFR50.67(Ref.7).

0/ReplaceSpecificActivityBaseswithREACTORCOOLANTSYSTEMInsert1 The maximum allowable doses to an individual at the exclusion area boundary (EAB) distance for 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> 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 <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> 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).

0/67 0/~  !!5~ ~ ~ 70 0/ 58ThisELowestEYerviceETemperatureEvalueEofEKZ[°\EalsoEincludesEanEadditionalE]°\EtoEaccountEforEtemperatureEmeasurementEuncertaintyH 0/300 0/TS 3.5.2.d requires that an ECCS subsystem(s) have OPERABLE chargingpump and associated flow path from the BAMT(s). Reference to TS 3.1.2.2requires that the Train A charging pump flowpath is from the BAMT(s) throughthe boric acid makeup pump(s). The Train B charging pump flowpath is fromthe BAMT(s) through the gravity feed valve(s).

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gaseousradioactivewasteinventoryinaeffectivedoseequivalent 1BranchTechnicalPosition11-5,"PostulatedRadioactiveReleasesDuetoWasteGasSystemLeakorFailure,"ofStandardReviewPlanChapter11, RadioactiveWasteManagement,"ofNUREG-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."