ML20101Q601

Proposed TS Figure 3.6-1 Re Containment Internal Pressure, Average Air Temp & Relative Humidity Limits & TS Figure 3.2-1 Re Linear Heat Rate Limit

ML20101Q601
Person / Time
Site:	Arkansas Nuclear
Issue date:	07/09/1992
From:	ENTERGY OPERATIONS, INC.
To:
Shared Package
ML20101Q594	List: 2CAN079201, Application for Amend to License NPF-6,changing TS to Revise Containment Internal Pressure,Average Air Temp & Relative Humidity Limits in TS Figure 3.6-1 & Bases & Reduce Linear Heat Rate Limit in TS Figure 3.2-1 ML20101Q601
References
NUDOCS 9207150022
Download: ML20101Q601 (4)

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1 PROPOSED TECilNICAL SPECIFICATION CllANGES f i- ) ap \\ I-, t ;;O j y s L j :; > :: c, Ifi i i ihkEIfhj22920709 P CK.D5000368 r. PDR a..

3 i w 14.0 9 l C' .g E C i 35 g-. .g i 5-m m rA No C y 13.0 <m mm ZQ mO l <2 I W+ bQ s< l $d UNACCEPTABLE OPERATION R E+ 12.1 12.0 ACCEPTABLE OPERATION mm n Jo b b i Od I ir 11.0 h 0 100 200 300 400 500 E e EFFECTIVE FULL POWER DAYS z Figure 3.2 - 1 l g b ALLOWABLE PEAK LINEAR HEAT RATE vs. BURNUP (COLSS OUT OF SERVICE)

? 1 8 .} _ < q.,_ q _ _. {<,_1. Q _. _ _4 ,_. 4._- ..7,-_{-{ r = _._{mL.. -y _._.._.4- .. __ p. ...~p-,_.- 4 _j__ ._.-L.., + 4_ .~... ~.4 ...~. _j.. . m. ._.M_.I2 .. _ [3_ LL _.- 2 ^_...- 1 .$$ 2T .1 2 REGION OF UN g 37 2 ::2: g 2 21. .ACCE.PTA g.E OP,ER ATIOft ,_C. ' k _l.y. .7 '~" 212.7222 3 ..7. - - q_.m.. (/) 2 - (100,16.19)b.-f- -y H C t.A'IIV E I'"TI221h- "~'~" ~ ^ 2 2222~" ' f/) 160.16.19) d '@0,16.06)LLJJ.J 1 j (100,16 05)k 1 22 2..HUMIDliY '-7--"--- % o.s u, H + r m i o oo.i u >I M.2tg[:. jjii [ 16 - n J q._ ._-,_ L, I.q.~.4 -100% q, a 50% ~~~" ...i. Q% { .. _. 9. y., t ...p.,_ p gy 4,4 +... .._ y 4 ' 4. 4, c.g g 1 .r. 4... 15 _= ... +. .J- - -t - N >(140,14 0) -. y 2 [2 22[ 1,5 ((21.... T[. C I I I d-LU ,'+._ i(l40,,14.46) m ,(14(1 g t 4.4) 1 _ D-. ~ _. : R E GI O N O F A A....w.,... +.~.-. -2,, p,.a t i4.2i>,_._. d i r )Q 14 - ACCEPIABhE_O.P_ ERAT!ON_ 4 44 =4 ._...;;1. f g 1 _ 4. 4-j 9 n--- -y g, o 4'.L4 '4.'+ 1mi- .i.1 13 -- _.,..4-.. 4.. '(60,12.8) + + Fr (t20, t u") - -th---- -r-'- i -~- y r 12 0 ' 4 1 i ' l qTTTTi l l i iTT T i l i l i l l f l i l, l l 11111l l, I i l 60 80 100 120 140 160 CONTAINMENT AVERAGE AIR TEMPERATURE ( F) FIGURE 3.6 - 1 CONTAINMENT INTERNAL PRESSURE vs. CONTAINMENT AVERAGE AIR TEMPERATURE ARgANSA8 - UNIT 2 3/4 6-7 Arnendment No. 7, # ^

(t e. 7 CONTAINMENT _SYSIfMS-BASES 3/4.6.1.4 JRIESSAh.fREESDEfu_ AIR TEtifERAIMEL.WilLlX1dI1YE 1MillllIX 'The If mit ations on contalna. ant internal pressure, averago air temperature and relative humidity ensure that 1) the contalnuent st.ructure is provented from exceedi..g its design negativo pressure differential with respect to the outsido atmosphero of 5.0 pnig 21 the containment peak l pressure does not exceed the design pressure of 54 psig during design basis conditions, and 3) the ECCS analysis assumptions are maintained. The limitation on containment averago air temperature ensures that thn containment liner plato temperaturn does not exceed the design temperature of 300*F during h0CA conditions. The cont.ainment t emper n t.u re limit is consiste.pt with the. accident analyses..Figuro 3.6-1 reprnsents analysis limits and does not account. for instrument error. 2/4.6.1.5 CONTAJRtifdT STRUCTURA U NIEGRil! This' limitation ensures that the structural integrity of the contalnment will be maintained comparable to the original design standards for the life of the facility. Structural integrity is required to ensure that the containment; will withstand the meximum pressure of 53.4 psig in the event of a h0CA. The visual examination of tendons, an'..horagen and containment surfaces and the Type A leakage tests of the Unit 2 containment in conjunction with the required wurveillan e activition of the Unit 1 containment are sufficient to demonstrato t.his capability. The surveillanco requirements for._ demonstrating the containment's structural -integrity are in comp 11anco t.lth - tho-recommendat f ans of Regulatory Guide 1.35 "Innervice Surveillanen of Ungrout ed Tendons in Prostressed Concrete Containment Structures",' January 1976. T 2/4.6.-l.6 GONI41Rt1ENT.. VERI 1LATION jiYSIfd The containment purgo supply and exhaust isolation valvna are required to be closed durin<; plant operation since' thosn valves have not been demonstrated capable of closing.during a LOCA. Maintaining these t valves closed during plant operations ensures that excessivo quantities of radioactivo matnrials will not be relonsed via the containment. purgo system. e 5 p 4 -ARKANSAS - UNIT 24 11.3/4 6-2_ Amendment No.}}