ML20043A253
| ML20043A253 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah  |
| Issue date: | 05/15/1990 |
| From: | TENNESSEE VALLEY AUTHORITY |
| To: | |
| Shared Package | |
| ML20043A240 | List: |
| References | |
| NUDOCS 9005210093 | |
| Download: ML20043A253 (16) | |
Text
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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 ;
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w , m O TABLE 2.2-1 (Continued) ^ C
.o REACTOR-TRIP SYSTEM INSTRUMENTATION TRIP SETPOINTS - '
w _w_w_ _ 8 .
,. ~ ,
FUNCTl0NAL UNIT ... g TRIP SETPOINT Rl
; p p ea . . .ad4
+, ALLOWABLE VALUES
[ 1 5 cf n:rr u rang; in;tra ent mg i n ;f . rr.,.; r;ng; in:trx st
- 13. Steam Generator Water .
y Level--Low-Low R20 - cpan ::ch :t::: g=:rsicr :
- p n ::ch :t =' g:::r:t:r 14.-Ste=/F::1::ter F?=
c' 44mma+m,...a.,..c,.,,._.
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- '2.
_ . _x _ . n..mr.m.,5% ;f f=1? :t:= f!= :t -
.- . nn.aro.,
m m_ _ :. ._. ... r ..
/705 -Gener:ter Water level uith ste:: generatcr unter I ::1 r. .u.ron.,or a- . o.....-..,1.__:.m._... __
DeleM .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- :: :te:: g =rator 1 ^
- nt : pan :::ch :tta gstrator-
- 15. Undervoltage-Reactor Coolant Pumps 1 5022 volts each bus l'4739 volts each bus 89 ry 16. Underfrequency-Reactor .
. 1 c4
. m Coolant Pumps 1 56.0 Hz each bus 1 55.9 Hz each bus 4
- 17. ~.arbine Trip i
A. Low Trip System 11 45 psig :143 psig . Pressure B. Turbine Stop Valve
._> 1% open-Closure .
_> 1%'open 18.'. Safety Injection. Input- Not Applicable from ESF Not Applicable
- 19. Intermediate Range ~ Neutron l'.1x1010jamps T g, -11
' Flux - (P-6) Enable: Block ~1'6 x 10 amps 1g Source Range Reactor Trip ge
- , . ' T "E 20. Power Range Neutron ~ Flux iJ.4%
" < 10% offRATED' (not P-10) Input to Low Power. THERMAL POWER
<-14& of RATED Reactor Trips Block P-7
." E
" -- THERMAL POWER- '
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TABLE 3.3-4 (Continued) E g "~SETP0iNTS. ENGINEERED SAFETY FEATURE ACTUATION SYSTEN INSTRUMENT 4 TION'TR'IP ( 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*
{ d. S. I .- See liabove (all SI Setpoints)- , Y e. Station Blackout
-O 0 volts with"a 5.0Lsecond 10 volts with a 5.0 i-1.01.second time delay time.. delay'
- f. .Tri:4 if Main Feedwater N. A. N. A.- -
i Pum s
- g. -Auxiliary Feedwater Suction Pressure-tow > 2 psig (motor driven pump) 11 psig (motor' driven pump)~
_ ' l
> 13.9 psig~-(turbine driven: . 1 12 psig-(turbinefdriven
~
R98 - pump) .- . pump) .. S" i h. As iliary Feedwater Suction: 4 seconds (motor. driven.
-- 2 3 Tran>fer Time Delays 14 seconds i.0.4Aeconds; !
. pump) . (motor driven ptmp):
13 .. 5.5 seconds (turbine' driven- :5.5. seconds 0.55 seconds-3@ pump)~ ' "I33
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L v, m - TABLE 2.2-1 (Continued)~ n . 8
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-< REACTOR TRIP SYSTEM IN'STRUMENTATION' TRIP SETPOINTS z
FUNCTIONAL UNIT TRIP SETPOINT g
. /, a.4 ,/ mrJ ALLOWABLE VALUES.
E 13. Steam Generator. Water s 18" qf nari s rt ;-. instrr;nt Q Level--Low-Low -Tren-esch ste r gsterater ' l " ef. ::. ;; ~r: ;; intr- : t R7-Tyyn-e r 5'ste- ;; :::ter to
- 14. c+ Octabac/ -- "+-- c'- -'<a'-<<" - * - - < ' - - + '
' ' = - < < " - * - - <i- ->
-Mismatch-and-Lew Ste r M^.TED T"E"t^L " DER ceinci&nt Generater Water Leve! eith ste r gener:ter' water ler:1 Y^.TE0 T"E""J.L ""'cR eeineitnt rith :te'r ;;; ret- r:ter leve!
-t 25*' Of narr= rrge in:tre- .
2 2 ef c: r-d r ~;- i Stre-ent spen--eec$ ste r generater :::t sp r- e r 5 ste r';;r.; rete- t,
- 15. Undervoltage-Reactor R76 Coolant Pumps 1 5022 volts-each bus 1 4739 volts each. bus. -
~~
- 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-Closure.
' > 1% open
- 18. Safety Injection Input Not Applicable
-from ESF -
Not Applicable-
- 19. Intermediate Range. Neutron 3.1 x;10 20 amps m . Flux, P-6, Enable Block ->6x1011l amps' '
3p Source Range Reactor' Trip
,. E s2.4 % ,' )S.$ g20. Power a.
Range Neutron Flux
- < 10% of RATED- '
(not.P-10). Input to Low THERMAL POWER ~< -H% of RATED' THERMAL.. POWER
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. _ 3 TABLE 3.3-4 (Continued) ^
E' SE ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTAlION TRIP'SETPOINTS
=
FUNCTIONAL UNIT TRIP SETPOINT ALLOWABLE VALUES-E 6. AUXILIARY FEEDWATER
-e .
a. ro 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
.(pump)
[12 (turbine driven ptanp) f84.
- h. Auxiliary Feedwater Suction '4'second, (mutor driven pump)
Transfer Time Delays ' ' 4 'secorids -!0.4 secorn!s (motor driven ptm.p) z> og 5.5 seconds (tu.bine driven pimip)3 5.5 secorne,'!O.55 second3.
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- ll PROPOSED TECHNICAL SPECIFICATION CHANGE' ;;" a. <
f --
- SEQUOYAH: NUCLEAR PLANT. UNITS 1 AND.2- 'l f;' .
f
-DOCKET NOS.-50-327.AND'i50-328 .
b
~
- i
- (TVA-SQN-TS 27 )' .>
3 i b , iDESCRIPTION AND-JUSTIFICATION FOR1 REVISION'TO3TS 89-27.
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ENCLOSURE'2-
'u N t i 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- .
, level (adverse'setpoint) TTD condition withJrespect to:the channel 4 L uncertainty allowances of Westinghouse, Electric Corporation'setpoint: methodology,-WCAP-11239 (transmitted.to.NRC by-letter dated. f L April 23,-1990, "Sequoyah Nuclear Plant:(SQN) . Eagle.21 Setpoint' Methodology - Westinghouse. Electric Corporation WCAPs 11239:and 11626").
~
l a The parameters that had potential for. impact were steam generator level i transmitter-environmental allowance and reference legJheatup environmental , allowance. -Original assumptions with respect to the transmitter-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. j The revised reference leg heatup environmental allowance: component is based on the maximum temperature in the' steam generator enclosure y .following a feedwater line break. A spectrum of break sizes'~and power j levels in which TTD would be used was investigated in. this _ study. i 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 l V i _ - . . -l
,e -
4 ,a
.. - l.
' 4
' )
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 to- . 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 l 1etter dated May 8, 1990, "Sequoyah Nuclear Plant:[SQN] - Eagle 211 1 Verification and Validation Final Report"). Thus; there is.no impact on l 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
. dated April 11,1990. "Sequoyah Nuclear Plant (SQN] --- Eagle 21 Unreviewed L 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
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