ML20042F251

Proposed Tech Specs Making Nominal Setpoint & Allowable Values Consistent W/Setpopint Methodology

ML20042F251
Person / Time
Site:	Sequoyah
Issue date:	04/25/1990
From:	TENNESSEE VALLEY AUTHORITY
To:
Shared Package
ML20042F248	List: ML20042F247 ML20042F251 ML20042F253 ML20042F255
References
NUDOCS 9005080051
Download: ML20042F251 (21)

Text

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LENCLOSURE1:.'

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PROPOSEDTTECHNICAliSPECIFICATION;-CHANGEJ 1

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3

,SEQUOYAH;NUCLEARLPLANTUNITS$1ANDf21' T

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DOCKEi NOS cJ 50-327/ Afl0-- 50-328:-

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TABLE 2.2-1 N

~

C REACTOR TRIP SYSTEM INSTRUMENTATION TRIP SETPOINTS.

E Egk 21 h

FUNCTIONAL UNIT TRIP SETPOINT ALLOWABLE VALUES

[

1. Manual Reactor Trip Not Applicable' Not Applicable 2

27.V %

2. Power Range, Neutron Flux Low Setpoint - 5 25% of RATED Low Setpoint - < -26% of RATED H

THERMAL POWER TilERMAL POWER t

~

t//,Y %

High Setpoint - 5 109% of RATED High Setpoint 5-H9Tr-of RATED TilERMAL POWER THERMAL POWER

3. Power Range, Neutron Flux,

< 5% of RATED TiiERMAL POWER with

< 6.3% of RATED THERMAL POWER

"'8 liigh Positive Rate a time constant 1 2 seconds with a time constant 1 2 seconds

4. Power Range, Neutron Flux,

< 5% of RATED THERMAL POWER with

< 6.3% of RATED THERMAL POWER R48 liigh Negative Rate a time constant 1 2 seconds with a time constant 1 2 seconds

5. Intermediate Range, Neutron

< 25% of RATED TilERMAL POWER 5 30% of RATED THERMAL POWER Flux

6. Source Range, Neutron F1'ux 5 10 counts per second 5 1.3 x 105 counts per second 5

7. Overtemperature AT See Note 1 See Note 3

8. Overpower AT

..See Note 2 See Note /'f

/96V.8

9. Pressurizer Pressure--Low 1 1970 psig 14960 psig -

.2390.2

10. Pressurizer Pressure--liigh

< 2385.psig 5, M psig

11. Pressurizer Water level--High.5 92% of instrument span 5

f instrument span

,g c.

89.4 %

• ~89.17 Al '

i gx

12. Loss of Flow 190% of design: flow per loop

• 1-89% of. design flow per loop

• sn k?

• Design flow is 91,400 gpm per loop.

n

- -~

TABLE 2.2-1 (Continued) m REACTOR TRIP SYSTEM INSTRUMENTATION TRIP SETPOINTS.

4 ZI FUNCTIONAL UNIT TRIP SETPOINT All0WABLE VALUES SE 12.4 'A

$ 21.

Turbine Impulse Chamber Pressure -

< 10% Turbine Impulse

< -HWr Turbine Impulse (P-13) Input to Low Power Reactor Trips Fressure Equivalent Pressure Equivalent Block P-7 y 59-2.,Al+

37.V %

22.

Power Range Neutron Flux - (P-8) Low

< 35% of RATED

< -3fA of RATED

[QllERMALPOWER Reactor Coolant Loop Flow, and Reactor TilERMAL POWER Trip 7.6 7o 23.

Power Range Neutron Flux - (P-10) -

> 10% of RATED

> -9%r of RATED Enable Block of Source, Intermediate, TilERMAL POWER TiiERMAL POWER and Power Range (10w setpoint) Reactor Trips 7

" 24.

Reactor Trip P-4

. Not Applicable Not Applicable SL C.

25.

Power Range Neutron Flux. - (P-9) -

< 50% of RATED

< M of RATED Blocks Reactor Trip for Turbine TilERMAL POWER Ti1ERMAL POWER Trip Below 50% Rated Power NOTATION-NOTE 1:

Overtemperature aT ( N< AT, [K - K 5)[T( M -T'J.+ K (P-P') - f (al)}

2(1+tga y

3 y

1. +tS C+T5 y

4 l+ K5 iT ST 14=/-/g.

'< m I+551 yg where:

=+eg-compensator on measured AT 7

33 Bro Syp u

= Time constants utilized in the h $cE Itc-for AT,'.If 5'C5> 7 *3 *-

~

,r 4 s

2 e

r..-

AT,

= Indicated AT at. RATED TilERMAL POWER

'5 K

< 1.15 23 1

K,

= 0.011 L

- -. ~. _, -

a--.-.--

. =. _ - - - - -

TABLE 2.2-1'(Continued) m Eg REACTOR TRIP SYSTEM INSTRUMENTATION TRIP SETPOINTS Y

=

NOTATION (Continued)

E a

NOTE 2:

(Continued) i Time constant utilized in the rate-lag controller for T

= 10 secs.

T

=

pw Y3 STD

avg,

)

- o3 deH.d in Mctc I ggde j.+ 7 3 f

q

- c dcf-ined in "ctc 1 4

K

=

6 0.0011 for T > T" and K = 0 for T $ T" W

6 O

T

=

as defined in Note 1 o

T"

= -Indicated T,yg at-RATED TilERMAL POWER (Calibration temperature for AT instrumentation, ; 578.2 F)

S as defined in Note 1

=

f (AI) 2 0 for all AI

=

NOTE 3:

The channel's' maximum trip setpoint shall not exceed..its computed trip point by more than f5'

-Zpercents sr sjmen.

1.9 by/. 2I o n

$ $ pors en Tie <kal.s.

mm.~~

f

,,1 a;,,F.,Lll sol ewal ib m/~U I'? /***"l A "C"

Y""

~

w, y

7 3

$y

' / 7pereen/ A 7" span.

g..

g y wore s: <-zusser ~z, -

km? RI T' b T

ubll ii niis i iii TABLE 4.3-1 (Continued) g REACTOR TRIP SYSTEl1 Iris 1 Rut 1ENTATIOf4 SURVEILLANCE REQUIREMENTS Q

CHANNEL H0 DES IN M11CH 3

CHANilEL CHANNEL FUNCTIONAL SURVEILLANCE 3

FUNCTIONAL UNIT CHECK CALIBRATION TEST REQUIRED Dalehd 15.

Stecm/r cd.eatcr ric.; 'tizactch and S

n Q

1, 2 rM f3 g

Lc.. Stcc Ccncrator t!atcr Lcyci Z

16.

Undervoltage - Reactor Coolant N.A.

R gQ 1

Pumps 17.

Underfrequency - Reactor Coolant N.A.

R gQ 1

Pumps was. 70s 18.

Turbine Trip

=

A.

Low Fluid Oil Pressure N.A.

N.A.

S/U(1) 1 B.

Turbine Stop Valve Closure N.A.

N.A.

S/U(1) 1 19.

Safety Injection Input from ESF N.A.

N.A.

-M(4).R 1, 2 w

20.

Reactor Trip Breaker N.A.

N.A.

M(5) and S/U(1) 1, 2, and *

[

21.

Automatic Trip Logic N. A.

N.A.

M(5) 1, 2, and

• O 22.

Reactor Trip System Interlocks A.

Intermediate Range N.A.

R 4/U(0) N,/I, h

2, and

• Neutron Flux, P-6 B.

Power Range Neutron N.A.

-R- #. A.

S/"(0) NA.

L 1

Flux, P-7 C.

Power Range Neutron N.A.

R S/'.'(B) M4 1

Flux, P-8

).

D.

Power Range Neutron fl. A.

R _

{/L'(S) M4, 1, 2 Flux, P-10 E.

Turbine Impulse Chamber N.A.

R S/U(0)- M A-1

-G Pressure, P-13 h'{

F.

Power Range Neutron N.A.

R

-5/U(0) /V,//,

1 es-Flux, P-9 03 G.

Reactor Trip, P-4

'N.A.

N.A.

S/"(e) A 1, 2, and

• l R67 u"

F 23.

Reactor Trip Bypass Breaker N.A.

N.A.

M(10)R(11) 1, 2, and'*

R58 a

S

._= _.

TABLE 3.3-3 (Continued)

Mg ENGINEERED SAFETY FEATURE ACTUATION SYSTEM-INSTRUMENTATION O

E MINIMUM TOTAL NO.

CHANNELS CHANNELS APPLICABLE

~

E FUtlCT10t1AL UNIT OF CilANNELS TO TRIP OPERABLE MCDES ACTION w

8.

ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INTERLOCKS

~

a.

Pressurizer Pressure -

3 2

.2 1,2-3 22a

";i :' i: -P-1//ND7~ A'/pg9.T7 Al Neur a,f,y b.

', y g

a. '~'

a' a'

^

^~

u

,e, etu c.

~ Steam Generator 3/ loop 2/ loop 3/ loop.

1, 2 22c Level P 14

=any loop w

a w

9.

AUTOMATIC SWITCHOVER T0 CONTAINi.ENT SUMP ca a.

RWST Level Low 4

'2 3

1, 2, 3,'4 18 R67-COINCIDENT WITH Containment-Sump

. Level

.High.

4 2'

3 1,

2,'.3, 4'

18 AND Safety Injection

[(See :1 -above for Safety Injection Requirements)

'b.

Automatic Actuation

= 2.

1-21 1,.2, 3,'4L.

-15 R67

~

py

' Log ic --

'E@

s a.

. g -.

t=

.. o 3

.i s.

~'

s TABLE 3.3-4 (Continued)

M E

EflGIf1EERED SAFETY FEATURE ACTUATf0f1 SYSTEM IfiSTRUMEf1TATIOff TRIP SETPOINTS

?

FUflCII0flAL Uf11T TRIP SETPOI!1T ALLOWABLE VALUES

/7.

LOSS OF P0h'ER z;

a.

6.9 kv Shutdown Board Undervoltage Loss of Voltage 1.

Start.of Diesel Generators R33 a.

flominal Voltage Setpoint 4860.>olts 4860 volts +97.2 volts b.

Relay Response Time for 0 volts with a 1.5 second 0 volts witE a 1.5 +0.5 Loss of Voltage time delay second time delay 2.

Load Shedding a.

flominal Voltage Setpoint 4860 volts 4860 volts + 97.2 volts b.

Relay Response Time for 0 volts with a 5.0 second 0 volts with a 5.0 +1.0 t'

Loss of Voltage time delay second time delay -

u b.

6.9 kv Shutdown Board-Degraded w

4 Voltage w'

1.

Voltage Sensors 6560 volts 6560 volts + 33 volts

- 2.

Diesel Generator Start and Load Shed Timer 300 seconds

'300 seconds + 30 seconds 3.

SI/ Degraded Voltage Logic Enable Timer 10 seconds 10 seconds + 0.5 seconds 8.

LilGIllEERED SAFETY FEATURE l

ACTUATI0fl SYSTEll IllTERLOCKS.

a.

Pressurizer Pressure 1975.a 6j/e b EF

!!2~ ?! 9!}^fu/ canal:e 4 ef Safetl" !r ection "

~< 1970 psig

-< 49es-psig i

d b/cel e/ Jadij 2e.

la Nor b In t re *Ny Ae's"'e Q

g.g sayes e en 89-27 Af o

ev

_4 r i t -

n:, t g..,3cp specitj atjen_4,; te he 59%%t_

437 tup re?!ceing the 7p,# reggm!!ng

~

me-rown =vlae=v or u= nww.swn i; wrun -

.g u

w f-// ' [osa$c ~ /Yla$nal Blotl el h h.

A, 3

xy, e-.., n,:, it,,,

M'te r i m. *,,i,

m u

s

.._f

...--...o-w-wm

TABLE 3.3-4 (Continued)

Ng EllGItlEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION TRIP SETPOINTS Se 7

FullCTIO!!AL UtlIT TRIP SETPOINT ALLOWABLE VALUES E

8.

EllGillEERED SAFETY FEATURE ACTUATIOil C

SYSTEf1 IllTERLOCKS (Continued)

~

b.

D fald

-Preecnt: ":nua! B1cck cf Safety j.5lB Injecticr P-12

510 F 1 512*F s

Q DcLU c.

";rual Block of Safety Injection,

-Stear Lin I;clation, Bloch Stec-De p u

__ 5?O F

-. 53B"r s

A w

d.

Steam Generator Level 4

Turbine Trip, Feedwater Isolation P-14 (See 5. above) 9.

AUTOMATIC SWITCH 0VER TO CONTAltlMEllT sui 1P

.e-69-27 p/

R67 2 7/

a.

RWST Level - Low 130" from tank base 130" i f from tank base COINCIDENT Willi f,fJ "

Containment Sump Level '- liigh 30".above elev. 680' 30" 1 Jd!" above elev. 680'

- Afl0 '

n{

Safety Injection.

(See 1:above for all: Safety Injection Setpoints/ Allowable Valves) s o a

' E&

b.

A' omatic Actuation logic.

N.A.

H.A.

SS

. w-1*

OC 0 fosse w ns h n h u f g' d sk

.jk ; co,e hoher ko Aa,s.. to o,,

x2n ><..A s s/- K & j~ seco w l,.

ub7 ASb A '

T*,ne wvlne/ e$*$sd ss*,

sab-b _ ta,sbv/be.' b Ahnd*<< ~Slambe Aw-w Asd -// $

k

'f e f

)

i.s 7? 50.seco,ad.

r cw,-

c.=---

.ptw,'-~

y i-y-y

.y

...y,.,,

,s-%

,s 3

.9 et a

.u.

3 s

N

~

TABLE 4.3-2 (Continued)

E Ef!Gif1EEllED SAFETY FEATURE 'ACTUATI0ff SYSTft! If1STRUffEllTATION S'

SURVEILt AtJCE REQUIREfittelS 5'

CllANNEL t10 DES IN WillCil c

CilAfif1EL CllAfillEL FUf1CTIONAL SURVEILLANCE

}

FUtlCTICilAL UtlIT CllECK CALIBRATIOff TEST REQUIRED d.

6.9 kv Shutdown Board -

Degraded Voltage 1.

Voltage sensors S

R 1, 2, 3, 4 R33 2.

Diesel Generators it. A.

R fl. A.

1, 2, 3, 4 Start and Load Shedding Timer 3.

SI/ Degraded Voltage it. A.

R fl. A.

1, 2, 3, 4 t'

Logic Timer u

Y 8.

Ef1GIllEERED SAFETY FEATURE y

ACTUATI0ff SYSTEl-1 IllIERLOCKS[gg.yyg/

I a.

Pressurizer Pressure,

. fl. A.

R(2) fl. A.

1, 2, 3 P-11/NOT / //

RSI A

flea / MO I

b.

"^

'avo' c.

Ste m Generator fl. A.

R(2) fl. A.

1, 2 Leve,.P-14 fi' 9.

AUT0ilATIC SWITCl10VER'TO 2g C0fl1AIllilEllT SullP

,e 69-27A i SE 32 a.

f<5WI I evel - Lou S.

.R

-M-Q 1, 2, 3, 4

,7 COIllCIDEllT Willi Fif Containment Sump level - liigh S

R 4Q 1, 2, 3, 4 AllD

{t Safety. Injection (See I above f or all Safety Injection. Surveillance. Requirements) 1;.

Automatic Actuation Logic fl. A.

fl. A.

Ff(I) 1, 2, 3, 4 R67 5

14410:

this techr, ice! specif! Eat-ion-4e-be--imp!crented ::t the startup fe!!cs!ug the 2M r"f u=!!ng outaga

-Gr-54140ving-somydeMen-e! t!:c ~:di fisaMen&ishever is car'ier.

E w

s._.,

-, - - _ - - ~ -. -

.N -.

'~

TABLE 2.2-1 N

REACTOR TRIP SYSTEM INSTRUMENTATION TRIP SETPOINTS E!

E FUNCTIONAL UNIT TRIF SETPOINT ALLOWABLE VALUES

1. Manual Reactor Trip Not Applicable Not Applicable 4 2 Y 7.

2. Power Range, Neutron Flux Low Setpoint - < 25% of RATED Low Setpoint - <-26% of. RATED THERMAL POWER -

THERMAL POWER ~

III.1 %

High Setpoint - < 109% of RATED THERMAL POWER- -

High Setpoint

<-140% of RATED -

THERMAL POWER

3. Power. Range, Neutron Flux,

< 5% of RATED THERMAL POWER with

< 6.3% of RATED THERMAL POWER High Positive Rate a time constant 1 2 seconds with a time constant 1 2 seconds R36

4. Power Range, Neutron Flux, 5 5% of RATED THERMAL POWER with 5 6.3% of RATED THERMAL POWER R36 High Negative ~a a time constant 1 2 seconds with a time constant > 2 seconds m

c5

5. Intermediate Range, Neutron 5 25% of RATED THERMAL POWER

< 30% of RATED THERMAL POWER Flux

6. Source Range, Neutron Flux

$ 105' counts per.second 5

< 1.3 x 10 counts per second

7. Overtemperature AT See Note 1 See Note 3

8. Overpower AT See Note 2 See Note J'/

194V.s

9. Pressurizer Pressure--Low 1 1970 psig 1-1960 psig 2 3 7 0. a.

10. Pressiirizer Pressure--High 1 2385 psig 5 ii'395-psig 92.2 %

• ~

p

11. Pressurizer Water Level--High 5 92% of instrument span

< 0%r of instrument span G$

89A7, mg

12. Loss of Flow 2 90% of design flow 2 69% of design' flow e-69.274/

,g

- per loop *

=

per loop

• 5 E2

^0esign flow is 91,400 gpm per loop.

• o e

.a-n>.-n.>.

-_.e axwn-

---.w

.....~,..,w

.ae.sm.

... _. A Am

E

~

TABLE 2.2-1 (Continued) m g

REACTOR TRIP SYSTEM INSTRUMENTATION TRIP SETPOINTS Y

z FUNCTIONAL UAIT TRIP SETPOINT ALLOWABLE VALUES g

/2.4 %

7 21.

Turbine Impulse Chamber Pressure -

< 10% Turbine Impulse

<-H% Turbine Impulse (P-13) Input to Low Power Reactor Trips Pressure Equivalent Pressure Equivalent g

Block P-7 37y7 C E9-2 7 R t.

22.

Power Range Neutron Flux - (P-8) Low

< 35% of RATED

< -3fA of RATED Reactor Coolant Loop Flow, and THERMAL POWER THERMAL POWER Reactor Trip

~1. & *7.

23.

Power Range Neutron Flux - (P-10) -

> 10% of RATED

> M of RATED Enable block of Source, Intermediate, TiiEl: MAL POWER THERMAL POWER and Power Range (10w setpoint) reactor Trips 2

24.

Reactor Trip P-4 Not Applicable Not Applicable 52 1 %

25.

Power Range Neutron Flux - (P-9) -

< 50% of RATED

< -51% of RATED Blocks Reactor Trip for Turbine TilERMAL POWER -

THERMAL POWER Trip Below 50% Rated Power

',[ --

NOTATION Overtemperature AT ( M _< AT,'[K NOTE 1:

2 (I + r

)[T(

T'] + K (P-P') - f (AI)]

-K y

~3 y

G+tS f+T 5 y

4 D

x g where:

p 7 3 = Lag compensator on measured AT I

led.Q ab,Ilea g 2.

g 7,

= Time ~ constants utilized in the -hg cc ;;m:te-for AT, T = 2 secs, 7 = J aus.

r r

• f Af,

= Indicated AT at RATED TiiERMAL POWER.

[

.K

< 1.15 y

R21 g-K

= 0.011 2

e

TABLE 2.2-1 (Continued)

REACTOR TRIP SYSTEM INSTRUMENTATION TRIP'SETPOINTS "E

NOTATION (Continued)

EZ NOTE 2:

(Continued)

Time constant utilized in the rate-lag controller for T,yg, ty = 10 secs.

T

=

I defined ia Note -

= ac

.i *I4) r

- c defined i-Mete-4--

4 R 21 K

=

0.0011 for T > T" and K6 = 0 for T i T" 6

m O

T

=

as defined in Note 1 o

T" Indicated T,yg at RATED THERMAL POWER-(Calibration temperature for

=

AT instrumentation, 5 578.2 F)

S as defined in Note 1

=

~

f (AI)

= 0 for all AI 2

NOTE 3: The channel's maximum trip setpoint shall not' exceed its computed trip point by more than g

Z'percentx s T span, e

cn 49 g,

rn ll NOTE 4: T h e e b.,,,,/'s

,,mi,,ua )f.sa-/ o:.,1-4a//

,,o/ ana;,/ t/s to,ysL / 4 y.sc /p ai. f-b p

y 6 1,7 pen, f-e inoa

. spa n,

if iB8 A'DTE S: +.T,,u,}

6 "

$947 gl

- -..... ~.. - _ _ -,. _.. -. _..

TABLE 4.3-1 (Continued)

]m

. REACTOR TRIP SYSTEM INSTRUi1ENTATION SURVEILLANCE REQUIREffENTS E

5 Cl!ANNEL 110 DES FOR WilICil CilANNEL CilANNEL FUNCT10NAL SURVEILLANCE IS-7 FUNCTIONAL UNIT CllECK CAllBRATION TEST REQUIRED gy c

15. -Steam /feedwater410w-Mismatch and S

-tcu Ste r Cencrater W ter Lc/c!

Q 1, 2 R16 ro 16.

Undervoltage - Reactor Coolant N.A.

R WR 1

Pumps 17.

Underfrequency - Reactor Coolant N.A.

R

,M' S 1

Pumps 18.

Turbine Trip A.

Low Fluid Oil Pressure N.A.

N.A.

S/U(1) 1 B.

Turbine Stop Valve Closure N.A.

N.A S/U(1) 1 R

19.

Safety Injection Input from ESF N.A.

N.A.

MR 1, 2 w

20.

Reactor Trip Breaker N.A.

N.A.

M(5) and S/U(I) 1, 2, and

• M 21.

Automatic Trip Logic N.A.

N.A.

M(5) 1, 2, and

• 22.

Reactor Trip System Interlocks A.

Intermediate Range N.A R

-5/U (3} Md.

2, and

• Neutron Flux, P-6 B.

Power Range Neutron N.A.

-R-- N. A.

S/U (0) MA.

t1 Flux, P-7 C.

Power Range Neutron-N. A.

R S/U ( G ; N.d.

1 Flux, P -

D.

Power Range Neutron N.A.

R i

S/U (U) NJ.

1. 2 FF Flux, P-10 1

2@

E.

Turbine Impulse Chamber N.A.

R

g. &

Pressure, P-13 i'U ( O r,64, I

8 F.

Power Range Neutron a

Flux, P-9 N.A.

R Q/U (3) MA, 1

v.~ E G.

Reactor Trip, P-4 N.A.

N.A.

-t / " ( 3 1 /t

. I, 2, and *

$55

~

23.

Reactor Trip Bypass Breaker.

N.A.

N.A.

M(10)R(11) 1, 2, and

• 3.*

gg s

• m.

_.,n_was+~#--=---."*#'

M TABLE 3.3-3 (Continued) e S!

ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRIR-!ENTATIOff E

HitlIMUM c

TOTAL NO.

CHAf1TIELS CliANNELS APPLICABLE FUNCTIONAL UNIT z

OF CHAftttELS TO TRIP OPERABIE MODES ACTIOff m

8.

ENGINEERED SAFETY FEATURE ACTUATION SYSTEM ItiTERLOCKS a.

Pressurizer Pressure -

3 2

2 1,2,3 22a 39-27Af a -Net P-11/#T P-U Da LI.J b.

-T

- P-12 avg 2

3 I, 2, 3 224:

c.

Steam C-enerator 3/ loop 2/ loop 3/ loop 1, 2 22c y

Level P-14 any loop-u w

9.

AUTOMATIC SWITCHOVER TO CONTAINMENT SUMP o

a.

RWST Level - Low 4

2 3

1, 2, 3, 4 18 f55 COINC 9ENT WITH Conttiaznt Sump Lew. - High 4

2 3

1,2,3,4 18 AND Safety Injection (See 1 above for Safety Injection Requirements) o b.

Automatic Actuation 2

1 2

1, 2, 3, 4 15 gN Logic

!i E g35 b-g "B

m-728 G~

3.=

M

a D

s la s

s u

5 0

d d

ll s

s n

n i.

t0 t1 s

o o

l 1

l 1

t c

c e

lo o

l e

e u

v5 y

v 0. y o

s s

f v

m S

21 a 25a 0

5 L

l l

l 3

f i

7 ae iae

'i t

J-i l

9 d

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i SEQUOYAH - UNIT 2 3/4 3-28 Amendment No. 5.

55 December 31, 1987 i

r

I TABLE _4.3-2 (Continued) m5g EllGIffEERED SAFETY FEATURE ACTUATI0ff SYSTEM IriSTRUMENTATIOff g

SURVLILLAtlCE REQlilREMLflI5

=

~

s CHANNEL MODES FOR Wi!ICil c

CilANNEL CilAntJEL FUNCTIONAL SURVEILLANCE IS 5

FUNCTI0flAL Ut4IT CHECK CALIBRATI0ft TEST REQUIRED w

M.

6.9 kv Shutdown Board -

Degraded Voltage 1.

Voltage sensors S

R H

1, 2, 3, 4 2.

Diesel Generators N.A.

R N.A.

1, 2, 3, 4 Start and Load Shedding Timer 3.

SI/ Degraded Voltage N.A.

R fl. A.

1, 2, 3, 4

{

logic Timer T

8.

EllGINEERED SAFETY FEATURE M

ACTUATION SYSTEM INTERLOCKS a.

Pressurizer Pressure, N.A.

R(2) fl. A.

1, 2, 3 927Al P-11/Nor P-tj b.

T

!?

"^

9(2) 1, 2, 3

"^

gy c.

Steam Generator N.A.

R(2)

N.A.

1, 2 Level, P-14 E>

1. 2 9.

AUTOMATIC SWITC110VER TO

?E CONTAINMENT SUMP s

a.

RSWT Level - Low 5

R

.W Q 1, 2, 3, 4 COINCIDENT WITH

-E Containment Sump Level - liigh 5

R Jt-Q I, 2, 3, 4 f

Atto QM Safety Injection (See I above for all Safety Injection Surveillance Requirewents) u, b.

Automatic Actuation Logic fl. A.

II. A 11( 1 )

I, 2, 3, 4

W>

vs C.

MtMl+iS-leEh6IEal ";p0Cififat400--i-9 LO SC i g IC;;:_^iittd ? T I ;j' the S ta -t uj: f0?'O d M4f-4fr' ? t t ""^ ! " ? ' E ""j "'!.',"'-

• C-gg3 s'

ENCLOSURE 2 PROPOSED TECHNICAL SPECIFICATION CHANGE SEQUOYAH NUCLEAR PLANT UNITS 1 AND 2 DOCKET NOS. 50-327 AND 50-328 (TVA-SQN-TS-89-21)

DESCRIPTION AND JUSTIFICATION FOR REVISION TO TS 89-27

/

1 l

l

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ENCLOSURE 2 Description of Change Tennessee Valley Authority proposes to revise the Sequoyah Nuclear Plant (SQN) Units 1 and 2 Technical Specification (TS) Change 89-27, submitted January 24, 1990.

Specifically,thefo} lowing-revisionsaremade.

1.

The reactor coolant system (RCS) loss of flow (Table 2.2-1,-Item 12) allowable value is revised.

2.

The low RCS flow reactor trip permissive, P-8 (Table 2.2-1 Item'22)~

nominal setpoint and allowable value are revised.

3.

The overpower delta-T maximum trip setpoint (Table 2.2-1,_ Note 4)'is revised.

4 4.

The channel functional test frequency notation for_ reactor trip system interlocks (Table 4.3-1, Item 22) that have refueling outage frequency channel calibrations are revised.

S.

The pressurizer pressure safety injection block permissive, P-11 entries (Table 3.3-3, 3.3-4, and 4,3-2, Item 8.a) are revised.

6.

The automatic switchover to containment sump (Tables 3.3-4 and 4.3-2..

1 Item 9.a) contal; nent sump and-refueling water storage tank- (RWST) level allowable values and channel functional test Intervals are revised.

1 Reason and Justification for Change Changes I, 2, and 3 are made for consistency with the issued Eagle 21 setpoint methodology.

TS 89-27 was submitted in parallel with the issuance of the final setpoint methodology, and the corresponding _ values were changed as the result of the ongoing review by TVA and Wastinghouse.

Change 4 is made to remove redundant and unnecessary information from TSs. TS Definition 1.4 states that a cLannel calibration shall include a l

channel functional test.

Therefore, for functional items that are~

calibrated on a refueling outage frequency, the notation of'a refueling outage frequency channel functional test does not provide any useful H

information. Consequently, the channel functional test notation for functional Items 22.A, 22.C. 22.D, 22.E. and 22.F is revised to "N.A."-

This combination of calibration and functional test notation is consistent with the testing requiremcnts for the loss'of RCS flow in.two loops reactor trip (lable 4.3-1 Item'13).

Change 5 is made to clearly identify both the trip and reset functions of the P-11 safety injection permissive.

Inclusion of the P-11 block enable setpoint and allowabic value is warranted because the negative steamline pressure rate steamline isolation function is enabled.when safety s

i i

y

[

d

injection is manually blocked below 1,970 pounds per square inch gauge (psig).

The difference between the P-11 block enable setpoint and allowable value represents a rack drift allowance, and is the same magnitude as that of the NOT-P-11 automatic unblock.

The margin between d

the P-11 and NOT-P-11 setpoints reflect a one percent deadband to prevent i

" chattering" of the permissive.- The changes to the entry titles for the l

P-11 permissive are editorial in nature and are made for clarification.

Change 6 is made to reflect the improved rack drift term associated with-l the Eagle 21 system for the containment. sump and RHST level channels.

As j

indicated in~the Eagle 21 setpoint methodology, the calculation of these allowable values was not within the scope of work being performed by Westinghouse. TVA has completed the instrument accuracy calculations;for' the containment sump and.RHST level channels, and these calculations'are_

_i provided as Enclosure 3 to this letter.. The. rack-drift terms for these channels are consistent with those in the Eagle 21 setpoint methodology, 0.7 percent of calibrated span (reference Sheet 20 of Calculation.

TI 28-0013, containment sump; and Sheet 17 of Calculation TI 0015, 9

RHST). The calibrated span of the containment sump level channels is 0 to 240 inches (TI 28-0013, Sheet'12), which yields a rack-drift term of plus or minus 1.68 inches.

This in turn is applied to the nominal-setpoint for an allowable-value of 30 plus or minus 1.68 inches.

Similarly, the calibrated span of the RHST level channels is 0 to 387 inches (TI 28-0015, Sheet 11), resulting in a rack-drif t. term of plus or minus 2.71 inches, and allowable value of 130 plus or minus 2.71-inches.

The channel functional test entries for the containment sump and RWST level channels are revised for consistency with other channels that are processed by Eagle 21 and calibrated on a refueling outage frequency.

In summary, the revisions to TS 89-27 described above are made:to prosiae an accurate reflection of the SQN reactor protection system after implementation of the Eagle 21 upgrade.

The numerical revisions provide standard consistency with Eagle 21 setpoint methodology.

The= text changes a

provide clarity and remove redundant information-form the TSs.

As such,-

the revisions do not alter the conclusions drawn in the enviror. mental impact evaluation or the no significant hazards consideration submitted with TS 89-27.

- ~-

7 s:-

u b.:

sQ

,u

'i s

ENCLOSURE 3 i

a TVA CALCULATION-TI28-0013, CONTAI'NNENT SUMP LEVEL CHANNELS

.1

(887 900402:012)

-TVA CALCULATION TI28-0013. REFUELING HATER STORAGE TANK:(RWST)! LEVEL CHANNELS:

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