ML20043A253

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Revised Pages to Proposed Tech Specs Re Reactor Trip Sys Instrumentation Trip Setpoints & ESFAS Instrumentation Trip Setpoints
ML20043A253
Person / Time
Site: Sequoyah  Tennessee Valley Authority icon.png
Issue date: 05/15/1990
From:
TENNESSEE VALLEY AUTHORITY
To:
Shared Package
ML20043A240 List:
References
NUDOCS 9005210093
Download: ML20043A253 (16)
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{{#Wiki_filter:; <- w w t<' 4 /,9 '... J' ^ pp, u :y .,s z, v. ENCLOSURE 1.' ,.i ? I PROPOSED TECHNICAL SPECIFICA'iION CHANGE. JSEQUOYAH NUCLEAR' PLANT UNITS,l'AND 2, i -e

DOCKET NOS..'50-327'AND 50-328 t

(TVA-SQN-TS-89-27) ,N. t i - LIST! 0F: AFFECTED PAGES ' Unit 1 2-6'- 3/4:3-27 . Unit 2: ( 2-6 ~ '3/4'3 : i j "l L 'l 1 l: a. 9005210093 900515 ii.1; ADOCK05009]{7 :{ e q PDR 'j-t ..I ^ - 4 9

= w TABLE 2.2-1 (Continued) m ^ O C REACTOR-TRIP SYSTEM INSTRUMENTATION TRIP SETPOINTS - .o _w_w_ w FUNCTl0NAL UNIT ~, 8 g TRIP SETPOINT Rl p p ea ad4 ALLOWABLE VALUES [ 1 5 cf n:rr u rang; in;tra m ... +,

13. Steam Generator Water Level--Low-Low ent g i n ;f. rr.,.; r;ng; in:trx st R20 -

y cpan ::ch :t::: g=:rsicr

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c ' M of ful! te:: #!s at

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r..u.r a-.

on.,or o.....-..,1.__:.m._... DeleM uith ste:: generatcr unter I ::1 .with ste s g uer;tcr utter ~1;;;I 125% cf narr= range in:tru-1 2'. 5 cf ::rr rn ;;.in:tra-cent : pan- :: 5- :te:: g =rator

nt : pan :::ch :tta gstrator-1

^

15. Undervoltage-Reactor Coolant Pumps 1 5022 volts each bus l'4739 volts each bus 89 ry
16. Underfrequency-Reactor

. 1 Coolant Pumps 1 56.0 Hz each bus 1 55.9 Hz each bus c4 m 4

17. ~.arbine Trip i

A. Low Trip System 11 45 psig Pressure

143 psig.

B. Turbine Stop Valve ._> 1% open- _> 1%'open Closure 18.'. Safety Injection. Input-Not Applicable 1 from ESF Not Applicable

19. Intermediate Range ~ Neutron l'.1x1010jamps T g, Flux - (P-6) Enable: Block

-11 ~1'6 x 10 amps 1g Source Range Reactor Trip ge

,. ' T "E 20. Power Range Neutron ~ Flux

< 10% offRATED' iJ.4% (not P-10) Input to Low Power. THERMAL POWER <-14& of RATED ." E Reactor Trips Block P-7 THERMAL POWER-e- _~ l e%, 4v,g, 2I - m~ 00 CD

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4 TABLE 3.3-4 (Continued) mEg ENGINEERED SAFETY FEATURE ACTUATION SYSTEN INSTRUMENT 4 TION'TR'IP SETP0iNTS. "~ ( s = [UtCTI0llAL UtlIT TRIP SETPOINT~ ' ALLOWABLE VALUES'. C E 6. AUXILIARY FEEDWATER '82 a. Ilanual Not Applicable Not-App 1; cable b. Automatic Actuation Logic Not Applicable Not Applicable.- c. 11ain Steam Generator Water Level-low-low > I?*' Of narre.: r rg: .. > I M Of r rr-r r:ngr- ~yg,,f. "R,, T rir ment. spar ::: P In:ir:::at :;.cn :::P cte r generater

teer gencr:ter*

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? L v, n TABLE 2.2-1 (Continued)~ m 8 REACTOR TRIP SYSTEM IN'STRUMENTATION' TRIP SETPOINTS ~ z FUNCTIONAL UNIT TRIP SETPOINT g ALLOWABLE VALUES. . /,,/ m J a.4 r E 13. Steam Generator. Water 18" qf nari s rt ;-. instrr;nt ' l " ef. ::. ;; ~r: ;; intr- : t s Q Level--Low-Low -Tren-esch ste r gsterater Tyyn-e r 5'ste- ;; :::ter R7-14. c+ Octabac/ to -- "+-- c'- -'<a'-<<" - * - - < ' - - + ' ' = - < < " - * - - <i- -> -Mismatch-and-Lew Ste r M^.TED T"E"t^L " DER ceinci&nt Y^.TE0 T"E""J.L ""'cR eeineitnt Generater Water Leve! eith ste r gener:ter' water ler:1 rith :te'r ;;; ret-r:ter leve! -t 25*' Of narr= rrge i :tre-2 2 ef c: r-d r ~;- i Stre-n ent spen--eec$ ste r generater

t sp r-e r 5 ste r';;r.; rete-t,
15. Undervoltage-Reactor 1 5022 volts-each bus 1 4739 volts each. bus.

~~ R76 Coolant Pumps

16. Underfrequency-Reactor

-> 56 Hz each bus ^ '? Coolant Pumps > 55.9 Hz .each bus: as

17. Turbine Trip A. ' Low Trip System

>-45 psig > 43 psig Pressure 8. Turbine Stop Valve > 1% open- ' > 1% open Closure.

18. Safety Injection Input Not Applicable Not Applicable-

-from ESF

19. Intermediate Range. Neutron 3.1 x;10 20 amps

->6x1011l amps' . Flux, P-6, Enable Block m3p Source Range Reactor' Trip E ,' )S. g s2.4 %

20. Power Range Neutron Flux

- < 10% of RATED-a. (not.P-10). Input to Low THERMAL POWER < -H% of RATED' THERMAL.. POWER ~ .m+ Power Reactor Trips c

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i.. -.......-. c-n';: . _ 3 TABLE 3.3-4 (Continued) ^ E' ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTAlION TRIP'SETPOINTS SE >= FUNCTIONAL UNIT TRIP SETPOINT ALLOWABLE VALUES-E 6. AUXILIARY FEEDWATER -e ro a. Manual Not Applicable 'Not Applicable.. b. Automatic Actuation Logic Not Applicable 'Not Applicable c. Main Steam Generator ' T,,u d ' Y Water Level-low-low M 8T cf narr e r: ; >1'N' ef -5yre rany h tr ent tpan e c5 %tr=ent :pm e::!- Steer generater ste r p erat - d. S. I. .See 1 above (all SI Setpoints) e. Station Blackout ~0 volts with a 5.0 second 0 volts with a 5.'O '1 0 'second " time. delay- - time delaj-f. Trip of Main Feedwater N.A. N. A., Pumps g. Auxiliary feedwater. Suction > 2Tpsig. (motor drisen ptuns) [1psig.(motordrivenpimip) Pressure-Low > 13.9 psig (turbine; driven [12 (turbine driven ptanp) f84. .(pump) h. Auxiliary Feedwater Suction '4'second, (mutor driven pump) ' 4 'secorids -!0.4 secorn!s (motor Transfer Time Delays driven ptm.p) z> ~ Ri l f> og 5.5 seconds (tu.bine driven pimip)3 ga 5.5 secorne,'!O.55 second3. ES . (t ur bine d.'ivt:n ponp)- - "E a;? z mO) s g Y O. 4 p a. .m._.

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qf' x p, t,, 4 ..g .N i' ,3 lt t.! ; ' i; ,g e-7 ..s t 1 t 1 y ENCbASURE2-E t - ll PROPOSED TECHNICAL SPECIFICATION CHANGE' a. f --

SEQUOYAH: NUCLEAR PLANT. UNITS 1 AND.2-

'l f;' -DOCKET NOS.-50-327.AND'i50-328. f b ~

i

- (TVA-SQN-TS 27 )' 3i b iDESCRIPTION AND-JUSTIFICATION FOR1 REVISION'TO3TS 89-27. a ,L k Ji t .. c.'. lI -1 l- -l d 5 i t t f f . i 1 i .e. N.. i s e p

'y' y ~ 7{i l + '.; 1 ENCLOSURE'2- - m 'u N i t 1 u 1 A Description of' Change .] The steam generator water level adverse trip setpoints - (Table 2.3-1,-

Reactor Trip System Instrumentation Trip Setpoints Items.13.ai and b. and; LTable.3.3-4, Engineered
Safety Feature Actuation System' Trip 1Setpoints,
Item 6.c) care revised to account for;the steam generator reference' leg 1 heatup environmental allowance considering the effectstof
the~ trip = time; j!

delay-(TTD).:

Reason for Chanre, g

The: revised t' rip setpoints and' allowable. values. reflect the impacts of?the-f' TTD function on the' steam. generator reference leg heatup environmental l allowance..The' original TS 89-27 submittal provided corresponding' steam l generator setpoints that did not' consider the-interaction between TTD and-L reference leg'heatup. j ' Justification-for Channe [. 'As~ documented in a WestinghousefElectric Corporation' letter,' TVA-90-792, dated May 13, 1990,'an evaluation has.been performed tol determine'the-j ' impact.of: containment temperatures during a steam generator low-low water-4 level (adverse'setpoint) TTD condition withJrespect to:the channel uncertainty allowances of Westinghouse, Electric Corporation'setpoint: L methodology,-WCAP-11239 (transmitted.to.NRC by-letter dated. f L April 23,-1990, "Sequoyah Nuclear Plant:(SQN) . Eagle.21 Setpoint' l Methodology - Westinghouse. Electric Corporation WCAPs 11239:and 11626"). a ~ The parameters that had potential for. impact were steam generator level i transmitter-environmental allowance and reference legJheatup environmental -Original assumptions with respect to the transmitter-allowance. l-environmental allowance' continue to'be bounding:for-the TTD condition. s However, because of the delay in the generation as a reactor trip signal, l-the reference leg heatup environmental allowance must be calculated considering the effects of-the TTD function. The revised reference leg heatup environmental allowance: component is j based on the maximum temperature in the' steam generator enclosure y .following a feedwater line break. A spectrum of break sizes'~and power i j levels in which TTD would be used was investigated in. this _ study. L ? The mass energy release analysis reviewed two sources of mass' energy to i the steam generator enclosure. The first is the release that comes from i 2 the steam generator and the second'is the release that-comes from the main [ and auxiliary feedwater systems. The releases coming from the, steam generator were modelled to maximize >the - .i enthalpy of the releases that would force the highest temperatures in the steam generator enclosure. Main feedwater flow wasLassumed to.be available until 60 seconds prior to reactor trip. This analysis V i - l

,e ,a 4 - l. 4 ' 2- ) a .I conservat'ively assumed that for 60 seconds prior to reactor: trip, no main l feedwater. flow through the faulted feedwater~1ine was availablo. This. i assumption maximizes'the heatup of the' reference. legs'. The'604second time. period with no feedwater-flow is based on a maximum' delay of 30 seconds. -betveen the. time of both: main feedwater'pum'ps tripping and.thh time that

~

! auxiliary.feedwater is-initiated. / The. temperature transient offthe steam generator enclosure was'used'as'a i = boundary l condition to calculete'the temperature of the water in'the- -reference;1egs as a' function'of time. This' calculation. considered. material properties and; heat transfer characteristics of the. reference.legL andLits insulation. The maximum' reference: leg temperature prior 7 o-t reactor trip-was used to calculate'the reference leg.heatup-component.of ) Lthe' channel uncertainty.> i The results of:the transient and containment analyses were factored into a ~ recalculation of the environmental allowance associated with the heatup of the' steam generator reference-legs. :These calculations employed the configuration of the Sequoyah Nuclear: Plant (SQN)' reference' leg. j. insulation.'.Th'e'results indicated,that the-reference 11eg'heatup q environmental allowance associated with TTD results.in a maximum increase 'of 2.1 percent'above:the previously submitted setpoints andiallowable values..These additional allowances are applicable:to'onlyithe steam' generator low-low water;1evel adverse setpoints.since.the' reference' leg heatup environmental' allowance presently incorporated in the snornal setpoint calculation bound-thel reference leg heatup environmental allowance for normal containment-conditions. The steam generator low-low level adverse setpoint is-changed using the Eagle 21 man machine. interface (MMI) cart' parameter. update function for' the affected racks. Eagle 21 setpoints do not reside within'the li electrically programmable read only' memory (EPROM)1 components that have I undergone verification and validation as summarized in the Eagle 21 q L Verification and Validation Final Report WCAP-12588 (transmitted'to,NRC by. l 1etter dated May 8, 1990, "Sequoyah Nuclear Plant:[SQN] - Eagle 211 Verification and Validation Final Report"). Thus; there is.no impact on verified and validated Eagle 21' software. Like all Eagle ~21Lsetpoints and tuning constants, the'new setpoint is to be proven via/ printout 1of l setpoints and tuning constants that are resident withintelectrically erasable programmable read only memory.(EEPROM);in the' applicable racks. Thus, this setpoint change will have no impact on site acceptance test-procedures that hase been previously completed.? Additionally,.the. conclusions of Safety Evaluation SECL-89-863 (transmitted to NRC by letter L . dated April 11,1990. "Sequoyah Nuclear Plant (SQN] --- Eagle 21 Unreviewed 1 l. Safety Question [USQ]") that addresses the resistance temperature detector L bypass elimination,' Eagle 21 reactor protection system upgrade, new L steamline break, median signal selector, environmental allewance modifier, L and TTD modification continue to apply'without-change. j l. ~ t ~ Y1}}

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