ML20077H088

From kanterella
Jump to navigation Jump to search
Proposed Tech Specs,Extending Instrumentation Surveillance Intervals & Allowed Outage Times
ML20077H088
Person / Time
Site: Grand Gulf Entergy icon.png
Issue date: 06/26/1991
From:
ENTERGY OPERATIONS, INC.
To:
Shared Package
ML19302E732 List:
References
GNRO-91-00083, GNRO-91-83, NUDOCS 9107050141
Download: ML20077H088 (33)
v • d • e


Text

A t t n r:hmerit 3 to GNKO-91/00083 MARK-UP OF AFFECTED TECliNICAL SPECIFICAT10t1 PAGES FOR PCOL - 91/12 G9105101/SNI,1CFI,R - 22 9107050141 91O/ 22/>

ppR ADOCK 0000l}, lj$

P

fjl Cii//o -

l REACTIVITY CONTROL $Y$1 EMS

$URVEILLANCE REQUIREMENTS (Continued) 4.1.

demonstrat 3.1. 4 i ng:The scram discharge volume shall be determined OPERABLE by a.* The scram discharge volume drain and went valves OPERABLE When '

control rods are scram tested from a normal control rod configuration of less than or equal to 50% ROD DEN $1TY at least once per 18 months.

by verifying that the drain and vent valves: ',

1. Close within 30 seconds after receipt of a signal for control rods to scram, and. i
2. Open when the scram signal is reset.
b. Proper level sensor response by performance of a CHANNEL IUNCTIONAt TEST of the scram discharge volume scram and control rod block level  !

Tdays.

instrumentationatleastonceper)i ) '

~

1 I

i "The provisions of Specification 4.0.4 are not applicable provided this surveillance is performed at least once per 18 months.

GRAND GULF UNIT 1 3/4 1-5 Amendment No. 21 3 l

. = _ . _ _ _ .

NL-91/10 '

INSTRUMENTATION 3/4.3.2 ISOLATION ACTUATIOW T )Jpgf)'J/

LIMITINGCONDITIONFOROPERAlpg

...,..,_ ,., _m . _

3.3.2 The isolation actuation % w eantation channeis shown in Tabla 3.3.2-1 shall be OPERABLE with their trip setpoints set consistent with the values snown in the Trip Setpoint column of Table 3.3.2-2 and with ISOLATION SYSTEM RESPONSE TIME as shown in Table 3.3.2-3.

APPLICABILITY: As shown in Table 3.3.2-1.

ACTION:

a. With an isolation actuation instrumentation channel trip setooint less conservative than the value shown in the Allowable Values column of Table 3.3.2-2, declare the channel inoperable until the channel is restored to OPERABLE status with its trip setpoint adjusted consistent with the Trip Setpoint value.
b. -44h-%: cMer of--CRESf4LE ch3^^e h len-4han-eequ++ed-by-Ge-M4meum-3 A - -CPERABL-E-Ghanneh per '-it-4ynee cauirement f ar One trip systte-( p,.A.ngri u -f  ? ~-eenelhenA-*4-thh d200 th0 '^^ W ad 8-GM SN!I N and/4 4 W P4 Y*t0 h 3* * # Ped'
.: h ;r.
c. With the number of OPERABLE channels less than required by the Minimum OPERABLE Channels per Trip System requirement for both trip system.,

placeatleastonetripsystem*/inthetrippedconditionwithinone hour and take the ACTION required by Table 3.3.2-1. l SURVEILLANCE REQUIREMENTS 4.3.2.1 Each isolation actuation instrumentation channel shall be demonstrated OPERABLE by the performance of the CHANNEL CHECK, CHANNEL FUNCTIONAL TEST and CHANNEL CALIBRATION operations for the OPERATIONAL CONDITIONS and at the frequencies shown in Table 4.3.2.1-1.

4.3.2.2 LOGIC SYSTEM FUNCTIONAL TESTS and simulated automatic operation of all chcnnels shall be performed at least once per 18 months.

4.3.2.3 The ISOLATION SYSTEM RESPONSE TIME of each isolation trip function shown in Table 3.3.2-3 shall be demonstrated to be within its limit at least once per 18 months. Each test shall include at least one channel per trip system such Insert 6 that all channels are tested at least once every N times 18 months, where N is the total number of redundant channels in a specific isolation trip svetem.

kn4tugerable would channel calJte4e Trip Function to occur. needInnot thesebe cases,placed in the the inopacec tripped e channel shall be restor h to (PERABLE status within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> or tha-ACTION required by y Table 3.3.2-1 for that T~fit >ivnction shall be t #

    • The trip system need not be placed -

ipped condition if this would cause the Trip Function to o cu . hen a t p-syJtem can be placed in-the tripped condition wit ausing the Trip Functio?tuqur, place the trip systemwithJt inoperable channels in the tripped conditi g if both sy s1Te the same number cf inoperable channels, place either trip r, em in the tripped condition. -

GRAND GULF-UNIT 1 3/4 3-9 Amendment No. 69j

. - - .. . . - - . . - . = _ - . _ _ - _ _ - . - . . -- . ~ __ __. - . . - - --

e NL-91/10

. Insert _A_.To_Page_3/4 3-9 With the number of OPERABLE channels less than required by the Minimum OPERABLE Channels per Trip System requirement for one trip system:

1. If placing the inoperabic channel (s) in the tripped condition would cause an isolation, the inoperabic channel (s) shall be restored to OPERABLE status within a) 12hoursfortrfpfunctionscommontoRPS Instrumentatiot ;

and b) 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> for t rfp functions not common to RPS Instrumentation or the ACTION required by Tabic 3.3.2-1 for t he af fected t rip function shall bo taken.

OR

2. If placing the inoperable channel (s) in the tripped condition would not cause an isolation, the inoperabic channol(s) and/or that trip system shall be placed in the tripped condition within a) 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> for t rip funct.f ons common to RPS Instrumentation ;

and b) 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> for trip functions not common to RPS I ns t rumenta t.f on#.

i I

l G9105101/SNLICFLR_- 23.

i

= l l

l NL-91/10 Insert _B_To_Page_3/_4_3-9 l

  • Place one trip system (with the most inoperable channals) in the tripped condition. The trip system riced riot bo piriced iti the tripped condition when this would cause thn isolat ion to occur.

(/ Trip functions common to RPS Instrumentation are shawn in Tabic 3.3.2-1.

k l

l l G9105101/SNLICFLR - 24 l

L. . . ..,_- , __.~.;_,u........,_. --_

4 c)-

TABLE 3.3.2-1 g

7 1501All0N AC10ATION INSTRUNENTAi!M_-

q VALVE GROUPS MINIMUM APPLICABLE i e OPERATED BY OPERABLE CHANNELS OPERATIJMAL' 5'

i E IRIP FUNCTION o

j 'GNAL (a) PER TRIP SYSTEM (b) CONDITION ACI!ON

-+ 1.

P..IMARY CONIAIWi[NT 1501ATION

a. Reactor Vessel Watar tevel-Low tow, Level 2 6A, 7, 8, 10 IC IdI 2 1, 2, 3 and # 20
b. Reactor Vessel Water level-tow low level 2 (ECC5 -

Division 3) 68 4 1, 2, 3 and # 29

! c. Reactor Vessel Water Level-

tow tow tow, tevel 1 (ECC5 -

Division 1 and Division 2 SI "II*I 2 1, 2, 3 and # 29

d. Drywell Pressure - Hi E U 6A, 7ICII I. 2 1, 2, 3 20

" l

] e. Drywell Pressure-High.

8 A (ECCS - Division 1 and w

Division 2) SI "II*I 2 1,2,3 29 g f. Drywell Pressure-High l (ECC5 - Division 3) 68 4 1,2,3 29 i

g. Containment and Drywell Ventilation Enhaust

{ Radiation - High High 7. 2I 'I 1, 2, 3 and

  • 21

)

2

h. Manual Initiation 6A, 7, 8, Ifl(c)(d) 2 1. 2, 3 and 's 22

! 2. MAIN SifAM TINE ISOLATION D a. Reactor Vessel Water Level-

3 tow low tow, Level 1 I 2 1,2,3 20 l- @ b. Main Steam Line l

3 Radiation - Hi n ID IN

% I, 2 1, 2, 3 23 c ' Main Steam tine l 3 Pressure - tow 1 2 1 2 41 O d. Main Steam Iism h e.

Flow .High Cor. denser Vacuus - Low 1

I 8 1, 2, 3 21

2 1, 2,"* 3** 21 9

l 4

! o i' y 1A81E 3.3.2-1 (Continued) z 1501 Ai!ON ACTUATION INSTRUNENIAil0N g.

E r- 8'~~

VALVE GROUPS NINIMuN APPLICA8tE

  • 4 7 OPERATED BY CMRAStE CHANN[L5 OPERATIONAL d
f. TRIP FUNCil0N SIGNAL (a) PER TRIP SYSIEM (b) ACil0N CONDITION h o

l 2.' MAIN SlEAM llNE 150 TAT 10N (Continued) i e*

f. N in Steam Line Tunnel Temperature - High 1 2 1, 2, 3 23
g. Nin Steam Line Tunnel e

a Temp.- High 1 2' l . 2, 3 - 23 j h. h aual Initiation I, 10 2 1, 2, 3 22 f, 3. SECONDARY CONIAlt0ENT ISOLATION -

4 a Reactor Vessel h ter

! tevel-Low Law Level 2 N.A.I' II 2 1, 2, 3, and # 25 w b. Drywell Pressure - Mi M. A.I'II INI. 2 1, 2, 3 25 {

1 c. Fuel Handling Area N.A.III 2 1, 2, 3, and

  • 25 w Ventilatloa Enhowst  ;

4 Radiation - High High

d. Fuel Handling Area Pool Sweep Exheast i Radiation - Nigh High N.A.g)) 2 1, 2, 3, and
  • 25 r

1

e. Mwiual Initiation M.A.('}Id)Ih) 2 1, 2, 3 26
M.A.I' II 2 *

.g .

25 j 4. REACIOR WAI'.R CLEANtf SYSTEM 150 TAI 10N I

4. A Flow - High- 8 1 1, 2, 3 21 t
b. A Flow Tleer 8 1 1, 2, 3 21 I D c. Equipment Area Temperature - 8 1/ room 1, 2, 3 21

{ g high, O l l d. Equipment Arec a Temp. -

j h High' 8 1/ room I, 2, 3 21 i' ~d e. ' Reactor Vessel Wter I (b level - tow !ow, level 2 8 2 1, 2, 3

!. 3- 2/ l 2.

] '. y t 7

i I

e  ;

t

O

.g TABLE 3.3.2-1 (rantinued)

E ISOLATION ACTUATION INSTRtMENTATION C

r h.

VALVE GROUPS MINIMIM APPLICABLE S

[. OPERATED BY OPERA 8tE CHANNELS OPERATIONAL h 5

TRIP FUNCTION SIGNAL (a) PER TRIP SYSTEM (b) CONDIIION ACTION l

I ~ 5.

REACTOR CORE ISOLATION COOLING SYSTEM ISOLATION

i. RHR Equipment Room Ambient Temperature - High 4 1/ room 1, 2, 3 27
j. RHR Equipment Room a leep. -

High 4 1/ room I, 2, 3 27

k. RHR/RCIC: Steam Line Flow -

High. 4 1 1,2,3 27

{ m 1. Manua! Initiation 4( } 1 1,2,3 26

{" m m. Drywell Pressure-High 9(a) 1 1,2,3 27 j  ; -(ECCS-Division 1 and w

a Division 2)

6. RHR SYSTEM 150tATION 4
a. RHR Equipment Room Ambient i Temperature - High 3 1/ room 1, 2, 3 28 4
b. RHR Equipment Room a y Temp. - High 3 1/ room 1, 2, 3 28 i $

a c. Reactor Vessel Water Level - Low, Level 3 U 3 3(p) 2 2(p) 1, 2, 3 4, 5 28  !

31 N

d. Reactor Vessel (RHR Cut-in
y Perai ) Pressure -

8 High 3 I) 2 1, 2. 3 28

e. Drywell Pressure High 3 II 2 I, 2. 3 28
f. Manual Initiation 3 2 1. 2, 3 26

NL-m4 TABLE 3.3.2-1 (Continued)

!$0LATION ACTUATION INSTRUMENTATION ACTION ACTION 20 -

Be in at least HOT SHUTDOWN within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLD SHUTDOWN within the next 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

ACTION 21 -

Close the affected system isolation valve (s) withi, one hour or:

a. In OPERATIONAL CONDITION 1, 2, or 3, be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLD SHUTDOWN within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />,
b. In OPERATIONAL CONDITION ", suspend CORE ALTERATIONS, handling of irradiated fuel in the primary containment and operations with a potential for draining the reactor vessel.

ACTION 22 -

Restore the manual initiation function to OPERABLE status within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> or be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLD SHUTDOWN within the following 24 houca.

ACTION 23 -

Be in at least STARTUP with the associated isolation valves closed within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> or be in at least HOT SHUTDOWN within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLD SHUTDOWN within the next 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

ACTION 24 -

Be in at least STARTUP within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.

ACTION 25 -

Establish SECONDARY CONTAINMENT INTEGRITY with the standby gas treatment system operating within one hour.

ACTION 26 -

Restore the manual initiation function to OPERABLE status within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> or close the affected system isolation valves within the next hour and declare the affected system inoperable.

ACTION 27 -

Close the affected system isolation valves within one hour and declare the affected system inoperable.

ACTION 28 -

Within one hour lock the affected system isolation valves closed, or verify, by remote indication, that the valve is closed and electrically disarmed, or isolate the penetration (s) and declare the affected system inoperable.

ACTION 29 -

Close the affected system isolation valves within one hour and declare the affected system or component inoperable or:

a. In OPERATIONAL CONDITION 1, 2 or 3 be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLD SHUTDOWN within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />,
b. In OPERATIONAL CONDITION # suspend CORE ALTERATIONS and opera-tions with a potential for draining the reactor vessel.

ACTION 30 -

Declare the affected SLCS pump inoperable.

ACTION 31 -

Isolate the shutdown cooling common suction line within one hour if it is not needed for shutdown cooling or initiate action within one hour to establish SECONDARY CONTAINMENT INTEGRITY.

D

  • NOTES When handling irradiated fuel in the primary or secondary containment and during CORE ALTERATIONS and operations with a potential for draining the reactor vessel.

"" The low condenser vacuus MSIV closure may be manually bypassed during reactor SHUTDOWN or for reactor STARTUP when condenser vacuus is below the trip set-point to allow opening of the MSIVs. The manual bypass shall be removed when condenser vacuum exceeds the trip setpoint.

  1. y During CORE ALTERATIONS and operations with a potential for draining the l reactor vessel.

N With any control rod withdrawn. Not applicable to contrcl rods removed per Specification 3.9.10.1 or 3.9.10.2.

(a) See Specification 3.6.4, Table 3.6.4-1 for valves in each valve group.

GRAND GULF-UNIT 1 3/4 3-14 Amendment No. 70_,

j

l NL-91/10 Insert _ To_Page 3/4. 3_-14

      • Trip function common to RI'S Inst rumentation.

G9105101/SNLICFLR - 25 m__-_._m_ ___m __ _ _______.____.___ _ _ _ _ _ _ _ _ _ _ _ . _ _ . . _ _ _ _ _ _ - - _ _ _ _ _

NL-91[ID TABLE 3.3.2-1 (Continued)

!$0LATION ACTUATION INSTRUMENTATION NOTES (Continued)

(b) A channel may be placed in an inoperable status for up to W hours for required surveillance without placing the trip system in the tripped con- l ,

dition provided at least one other OPERABLE channel in the same trip system is monitoring that parameter.

(c) Also actuates the stanoby gas treatment system. i (d) Also actuates the control room emergency filtratiun system in the isolation mode of operation.

(e) Two upscale-Hi Hi, one upscale Hi Hi and one downscale, or two downscale signals from the same trip system actuate the trip system and initiate isolation of the associated containment and drywell isolation valves.

(f) Also trips and isolates the mechanical vacuum pumps.

(g) Deleted.

(h) Also actuates secondary containment ventilation isolation dampers and valves per Table 3.6.6.2-1.

(1) Closes only RWCU system isolation valves G33-F001, G33-F004, and G33-F251.

(j) Actuates the Standby Gas Treatment System and isolates Auxiliary Building

'enetration of the ventilation systems within the Auxiliary Building.

(k) L..*es only RCIC outboard valves. A concurrent RCIC initiation signal is reau.*ed for isolation to occur.

(1)' Valve 4 E12-F037A and E12-F0378 are closed by high drywell pressure. All other Group 3 valves are closed by high reactor pressure.

(m) Valve Group 9 requires concurrent drywell high pressure and RCIC Steam Supply Pressure-Low signals to isolate.

(n) Valves E12-F042A and E12-F0428 are closed by Containment Spray System initiation signals.

(o) Also isolates valves E61-F009 E61-F010, E61-F056, and E61-F057 from Valve Group 7.

(p) Oaly required to isolate RHR system isolation valves E12-F008 and E12-F009.

One trip system and/or isolation valve may be inoperable for up to 14 days without placing the trip system in the tripped condition provided the diesel generator associated with the OPERABLE isolation valve is OPERABLE.

GRAND GULF-UNIT 1 3/4 3-15 Amendment No. 70,

o y TABLE 4.3.2.1-1 z

150l AllON ACIDAllCN IN51RtMINTAllCN SURVElll ANCE REQUIR[MENTS 2*.

E r- CHANNEL OPERAil0NAL 5

m 7 CHANNil FUNCilDNAL CMNNE L CONDITION 5 IN milch -

@ IRIP IONCIION CHECK IEST cat!BRATION SURVillLANCE REQUIRfD

1. PRIMARY CONTAINMENT 150LAT10N
a. Reactor Vessel Water level -

tow Low, tevel 2 5 )( Q RI 'I 1, 2, 3 and #

b. Reactor Vessel Water level-Low tow, tevel 2 (ECC5 -

5

  1. Q R(C 1, 2, 3 and #

Division 3)

c. Reactor Vessel Water tevel- 5 g RI '3 1, 2, 3 and #

Low Low Low,tevel 1 (ECCS - i Division 1 and Division 2) '

d. Drywell Pressure - High 5 RI 'I 1, 2, 3 l U
e. Drywell Pressure-High (ECCS - 5 g[Q Q RI 'I 1, 2, 3 Division 1 and Division 2) 4 f. Drywell Pressure-High (ECC5 - 5

/r' Q R(c) 1, 2, 3 i rv Division 3)

g. Contaivment and Drywell

, Ventilation Exhaust Radiation - High High 5 Jr O A 1, 2, 3 arid *

h. NA dI NA 1, 2, 3 and *#

Manual luitiation

2. MAIN SifAM LINE ISOLATION
a. Reactor Vessel Water level - 1, 2, 3 3>

3 b.

Low Low Low,tevel 1 Main Steam Line Radiation -

5 #Q '

Mc) n High 5

[Q R 1, 2, 3

c. Main Steam Line Pressure - h $

3 1ow 5 ,af Q RI 'I 1 d Hain Steam tine iIow - High 5 g R CI 1, 2, 3 g e. Condenser vacuum - tow 5 JVQ NI 'I I, /** l'*

i i

4

m

, g TABtf 4.3.2.1-1 (Continued) z C Z g 150t All0N ACillAll0N IN5IRIMf MIAIION 3URVEILLANCE REQUIREMINTS y--

C g ,

i CHAT 4NE L OPLHATIONAL $

C CHANNEL FUNCTIONAL CHANNLt COND!IlONS IN WHidt b [

CAIIBRATION U 1

TRIP FUNCTION CHECK- TEST SURVEILLANCE RIQUIRED g 2. MAIN STEAM LINE 150 TAT 10N (Continued) ,

f. Main Steam Line Tunnel  !

, Temperature - High 5 g A 1, 2. 3 f

g. Main Steam iine Tunnel  ;

, a icep. - High 5 Qg A 1, 2, 3 h Manual Initiation NA M'I MA 1, 2, 3

3. SECONDARY CONTAINMENT 150LATION [
a. Reactor Vessel Water j_ 1 b.

Level - tow Low, Level 2 Drywell Pressure - High 5

5

[gg ,$( R< ' I R

IC 1, 2, 3 and #

1, 2, 3 l

w c. Fuel Handling Area Ventilation j E

Exhaust Radiation - High High 5 g Qg A 1, 2, 3 and

  • f
d. Fuel Handling Area Pool Sweep 4 Exhaust Radiation - High High 5 {I g A 1, 2, 3 and *

, e. Manual Initiation NA

  • } NA 1, 2, 3 and *
4. Rf ACTOR WATER CILANUP SYSTEM 150t AllON J l
a. A Flow - High 5 R 1, 2, 3
b. A Flow Timer NA q

\

Q([ '

Y Q I, 2, 3 [

t

c. Equi; ment Area Temperature - t High 5 A 1, / , 3 i

Q

d. Equipment Area Vetitilation '

g a Temp. - High 5

'Q A 1. 2. 3  ;

< 3 e. Re&4. tor Vessel Water 3

L Q ievel - low low, level 2 5 g R I. /. 1 9  :

n i

2'.  !

o t

4 I

l

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

ijIl j llll1j l ll I 1I1li IIlllI ll '. l 1l!l E{2hO -

l D

E OR l I iU L

WQ E #

ANR #

MI 3 3 5 3 3 3 3 3 1 3 1 s 0 E l SC . . . . . . . . . . . .

l NN 2 2 2 2 2 2 2 2 2 2 2 J A0A Rl 1 , . . . , . , , . .

Ei t 1 1 1 1 1 l 1 1 1 1 1 1 Pl I O0E NV GR CU S S I

N I

M E

R I N U O Q LI I I E ET C C R NA A A I (

NR A A N N R Q R R A A A A E AB C I I N

A DLA

) 1 C d 1 e 1 u E n V i R L t U LA n S [ N }

e NOT '

N C

(

1 O

I T

NIS ATE t

ON CT /QQ NM g (, / / / [

A U )

1 T

N F d e OG QQ QQ Q Q 2 E u N (

M n O }

3 I i I R t T 4 I n A S l o 1 E N iK C 0 I NC ( A 5 A NM L

B ME 5 5 1 5 N 5 5 5 5 5 5 A N AH N T O HC O M I C I E T T t 1 m t .

A A n 5 g - n U L e Y - a I O i S h r t ie C S b g e r

h n o b A I m G i p e t s m A N H u a i e A N M  ! s i b T O E l l t - s D m l l I

T T

S e

nh n e 0 0 w e

r t A

h a e nh n e

A Y ng n C c P s mg m ng n 1 S ui u i u oi o ui u 0 TH T n N F y ah ol i o T H T 5 P h o 0 l h g R R h 1 U e- eg n i 1 e p xi - e- eg N n ni o t T n y p EH t t n ni A i e iH ia A i a u ne n i e i H

E L r t t i t L e l S e- er e t r t L u - a t 0 r e n mu m u -

C R

E mt m aa a .

er ep t e t m i i t

i n

I n

5 1

E t e

c e

s u D s e e m t m

a e

br i

rue ipt us qe q ura ip u mt s aa o .

er ep t e t e T 5 p Se I l R S r i S T s E p Eh S p S e A m a O P e g nem T T w m l W ne n S u C C C o C r C e Ci n 0

N R

it a ia a

C n L a R I

C . .

I L C

I P C

IT C

I H C

iT a

i a

a l

i O M M S M O R 1 2 R R R R M M I T C C C N A A U E . . E . . . . - .

f R f. g h. i R a b c d e f g P

I R .

1 4. 5 o::p5 o g#7C3 w UE> Df3 i P

i 4 ,'
  • i  ! i I!

o g TABLE 4.3.2.1-1 (Continued) 4- z .. g P o

[ E ISOLATION ACTUATION INSTRtMENTATION SURVEILLANCE REQUIREMENTS (

!;; CHANNEL. OPERATIONAL

-9 h

& CHANNEL FUNCTIONAL CHANNEL' CONOIIIONS IN WHICH O

) 3 TRIP FUNCTION CHECK TEST CALIBRATIGN 4

i ) 5. REACTOR CORE ISOLATION COOLING SYSTEM ISOLATION (Continued)

SURVEILLANCE REQUIRED i h. Main Steam Line Tunnel A

Temperature Timer- NA Q 'Q 1, 2, 3

. i. RHR Equipment Room Ambient j-Temperature - High' S Qg 'A 1, 2, 3 f

l j. RHR Equipment Room a Temp. -

High- S g/ A 1, 2, 3 i M

  • k. RHR/RCIC Steam Line Flow -
l. Y High S Qg R IC) 1, 2, 3 m

a)

l. 1. Manual Initiation NA f) NA 1, 2, 3  ;

i

m. 'Drywell Pressure-High S  ; Q )( R(C 1, 2, 3

.(ECCS Division l'and I.

t Division 2) ( ,

.> 1 I

g 6. RHR SYSTEM ISOLATION e

' l

} a. RHR' Equipment'Roon Ambient (

!. Temperature - High 5 1

2 (Q(

A 1, 2, 3 j g b. RHR Equipment Room

/ / i j g a Temp. - High i a 5

lQ [

A 1, 2, 3  ;

c. Reactor Vessel Water ' Level - i /

R IC}

~

j [ Low, Level.3 5 I Qg. 1,2,3,4,5 i

l O d. Reactor Vessel (RHR Cut-in Permissive) Pressure - High 5 g/ R('} I , 2, 3 J-1-

p t 4

, , . * , < ~ .- . , , _ ~ w r,_. , ,, - . . . , . , . . _ _- . _ , , . .,_,....,r.y _ ,_ , - . . , . .

n

. a 8 IAstE 4.3.2.1-1 (Cunti.nsed).

'h a

1501 ATION ACTUAIION INSIRtSENIAll0N SURVElit ANCE REQUIRf18 TIS h W -5 T

c CH4feIEL

. OPERAII0 fat

{ CHAleIEL fuMCII0hAL CHAseI[L CONDIIIONS IN WICH g IRIP FUNCil001 CHECK TEST CALIBRA110N SURVEIti AflCE RIQt IRID

6. RHR SYSTEM 150t A11006 (Continued) l d
e. Drywell Pressure - High
f. Manual Initiation 5

Q RI 'I 1, 2, 3 MA g a) 88 4 1, 2, 3

  • operations with a potential for dsaineng the reactor vessel.

w **the icw condenser vecine M51V closure may be noncelly bypassed during reactor SHUIDOWN or for reactor ,

E STARIUP when condenser vacuum is below the trip setr.sint to allow opening of the MSIVs. The manual

  • bypass shall be removed when condenser vacuse exceeds the trip setpoint.
  1. During
    1. With CORE any ALTERATI00s control and operations with a potential for draining the reactor vessel.

rod withdrawn.

or 3.9.10.2. 06et applicable to control rods removed per Specification 3.9.10.1 (a) Manual initiation switches shall be tested at least once per 18 months during shutdown. All ott.er N circuitry associated with manuel initiation shall raceive a CH40NIIt FUBICTIONAL IL5T at least ome perpf days as part of circuitry required to be tested for automatic system isolation.

(b) Each train or logic channel shair be tested at least every otherydays.

(c) Calibrate trip unit at least once per,2f days. 4 m

a 3 @- -

3 3

a i 3

-t-E

?

1

! (i!  ;  ; ' 'I !i :l : llltL[ t* ,! ; ,l

  • r1 9_hO l

N O

I e cn _

T C 331442 0 0 0 0 ni a

A 333333 3 3 3 3 0

3 il l e l n en ve

  • * * * $ 5 5 rh 5 5555 5 5 u st E ge EAS L * *** * * *
  • dL ib s

LNN 4 4444 4 4 4 4

4 eB rA poa n BOO , , ,,, , iR th AI! 333333 uE 5 t CTl 3 3 3 3 3 qP 3d IAi , , ,,,, , eO 1 er LRc , ,

r 3 re .

pen 222222 2 2 2 2 2 r oit PPo , , .,,, f e 5 t ua .

AOC 111111 1 1

oh 3 qe _

1 1 1 t l er so arg -

d r u .

N O

)

ee o qtt I

E

  • t I f n 2 eon ne T 8RN ro r A AEO e pt 5 eeu m T RPI rr N E T s 3 nat .

))))) ga a

E PSC bbgd ne n sg N

S OLN I EU (((((d 442221 il r o hnni t eI s I

SWf 4 4 4 4 4 ut i t p T t st e S GW f f P da a s a g0 N IHI sd c . ein0 I NCR t

) I T re ud iL El t ir a6 d N M tBsn n e O oi cAiI ea u

i t

n n

I T

A U 2 (o grhv o

o p

eR pE e li t SPOuu raw dh s

o T

tn r snes C .

eesah e C A l e pi o .y pb e M tl

( rl r M v ut en 1 e E o pd n e eanor E i t o tt

- T L 8 rd a s u 3 S l on 3 S Y w

, l e

  • forev.re.Adm cenl yE rReohes d g v l s e

o v s teal Pi 3 G L e edegvnOumHl ier p

N .

L wh tem apal e o qa E

L I

w ,og tpregsbrt eee- rr B

L O o hLi sfrpeevos asre sett eo A O l g- H fl - et rac T C - Mel l tdcaihl ti ruwa os E - ve bee svdtt sl r e R

O l

ef l ev eL eL ahhni rtt ednrearse encee C vfv e e e e t ehek LgLnr g g g e g e g pngspf uprei m e P set h Y

C f ae t a

t a t a a a oinimt ql n ivuceunl -v l rNrTt t t m ri pe r g e h N e e e l l l l i

rt e l E

G R i et edNn t

n,t i eg al o i v r)r eee o

v e

v) re e

v r) v) e re ntt e yneP eed S

s t md C pi F w r c w s

s eh-a, t oi E r rei d gd )d a eg eeee d gd s lasetNumEL SEDat en I

E l el oet esetPa nandnt nant .

p ie sa pe 0f re I

sssS UtUeul utui t eA o d D ses nt f l h o l e df scsSslR e ri o o C yb E n e di c

T ereeain 2sesSsV uVu u sosV ct slPsaP ot n S VPWtf asI d G uVe a mscM Y

S rl rss n f SdSd a e B fsd e l eea ef cOiai t co Nel enel a VoVeVd k VoVd pht t s e tot ot hi pb ne dci c P E T tet ere 1 s kLka k ka e yh p I

R cwcdpu S ayanpn a 6s6P6g r 3 6ssg s r b gn s tlt naofI nunt T Y ereoe e t n e n e aee t i S e 1. Le 1. 901. B e 1. Le l. s yipsnnhn nho 3 RDBCSI ut l 4(4(4( t ncieggwedot p S e s s 4(4( aartii heiit I

N I

I C p i v i v l p ltessewrt m- l we i c s t G P '. . . . . .r i . a et s sb d u eE T

1 I S Nabcdef o D s b c

. i Da t

= tmceeaeqjt8

=

C I

S I

V s s

=

hh s a a. i i l lddcrea8 es evvie rl Al F

n I D 1 o . c t e s o o p gt e ER e v t 1 2 ihl rrpeohP e P

I AwtAPPARNTOl R .

. ) )))

T C o a bcd *

( (((*

  • 8N s

e*h g3h**' q* yg [ g [ g ,o. .

.- I

,;j ; ,' ;il'

NL-(tI/lo

, INSTRUMENTATION TABLE 3. 3.3-1 (Continued)

EMERGENCY CORE COOLING SYSTEM ACTUATION INSTRUMENTATION ACTION ACTION 30 -

With the number of OPERABLE channels less than required by the Minimum OPERABLE Channels per Trip Function requirement:

a. With one channel inoperable, place the inoperable channel in the tripped condition within -

associatedsystem(s) inoperable.fnehour-ordeclarethe l M4 hhrb

b. With more than one channel inoperable, declare the associated system (s) inoperable.

ACTION 31 -

With the number of OPERABLE channels less than required by the Minimum OPERABLE Channels per Trip Function requirement, hr.>wg. > declare the associated ADS trip system or ECCS inoperable.

l ACTION 32 -

With the number of OPERABLE channels less than required the Minimum OPERABLE Channels per Trip Function requirement . our restore the inoperable channel to OPERABLE status withi W heurs l or declare the associated A05 trip system or ECCS inoperable.

ACTION 33 -

With the number of OPERABLE channels less than required by the Minimum OPERABLE Channels per Trip Function requirement, place the inoperable channel'.s) in the tripped condition within one-

-hove-or declare the HPCS system inoperable, ACTION 34 -

gg With the number of OPERABLE channels less than required by the Minimum OPERABLE Channels per Trip Function requirement, place at least one inoperable channel in the tripped condition within

-or^ hour or declare the HPCS system inoperable.

w.rs g ACTION 35 - With the n r 6 TOP)ERABLE channels less than required by the Minimum OPERABLE Channels per Trip Function requirement, place the inoperable channel (s) in the tripped condition within-one--

-hove-or declare the associated system (s) inoperable.

GRAND GULF-UNIT 1 3/4 3-30 Amendment No. 69j

j.

4 4

n -- TABLE 4.3.3.1-1 i j EMERGENCY CORE COOLING SYSTEM ACTUATION INSTRUMENTATION SURVEILLANCE REQUIREMENTS z I-lg CilANNEL OPERATIONAL i l g; CHANNEL FUNCTIONAL CHANNEL CONDITIONS FOR WHICH

'a TRIP FUNCTION CHECK TEST CALIBRATION SURVEILLANCE REQUIRED

$o i i-h A. DIVISION I TRIP SYSTEM' l* :1. RHR-A (LPCI MODE) AND LPCS SYSTEM I .

a. Reactor Vessel Water Level - r i Low Low Low, Level 1 S g R(a) 1, 2, 3, 4*, 5*

4

b. Drywell Pressure - High S gq R(a) 1, 2, 3 i- c. .LPCI Pump A Start Time <

! d.

Delay Relay Manual Initiation NA NA yp R

i Q

NA 1, 2, 3, 4*, 5*

1, 2, 3, 4 * , 5*

e. Reactor Vessel Pressure -

, low (Injection Permissive) S ,Wh RI *) 1, 2, 3, 4 * , 5" 1 2. AUTOMATIC DEPRESSURIZATION SYSTEM 1

y 1 RIP SYSTEM "A"#

,.S a. Reactor Vessel Water Level - .

Low low Low, level 1 5 )f' Q 1,2,3 i b.

c.

Drywell.' Pressure-High ADS Initiation Timer

'S X(

X' (Q

Rf8 R 1,2,3 NA Q Q 1,2,3 l d. Reactor Vessel Water Level - (

,W RI' Low, Level 3 5 *3 1, 2, 3

e. LPCS Pump Discharge Q '>

,M'qI RI ,)

Pressure-High 5 1, 2, 3

f. LPCI Pump A Discharge * .

Pressure-High 5 R I) 1, 2, 3

'; g. Manual Initiation NA %b R NA 1, 2, 3

, h. ADS Bypass Timer (High

,g I .' g Drywell. Pressure)

i. Manual Inhibit NA NA Xh R

Q HA 1, 2, 3 1, 2, 3 l

.E g -

j -

- O '

.i ~

!v"

-}

- . . - . . . = . .. .. -.

3 j

TAB _LE_4.3.3.1-1 (Continued)

- 5 g EMERGENCY CORE COOLING SYSTEM ACTUATION INSTRtMENTATION SURVEILLANCE REQUIREMENTS i- o 7 CitANNEL E CHANNEL FUNCTIONAL CilANNEL OPERATIONAL 7 i g7 TRIP FUNCTION-CONDITIONS FOR WHICH d i'$ B. DIVISION 2 TRIP SYSTEM CHECK TEST CALIBRATION SURVEILLANCE REQUIRED g w 1. RHR B AND C (LPCI N00E)

a. Reactor Vessel Water Level -

. b.

Low Low Low, level 1 Drywell Pressure - High S

5

,K X

h qd R

R 1, 2, 3, 1,2,3 4*, 5*

c. LPCI Pump B Start Time Delay Relay NA-
d. Manual Initiation NA  %'

R Q

NA 1, 2, 3, 4 * , 5*

1,2,3,4*,5*

e. Reactor Vessel Pressure -

l, Low (Injection Permissive) S Xh Rf *) 1, 2, 3, 4 * , 5*

2 l i T.

n 1 '

1 6

I i

s e-a

?

-, En

.D O

, I i

NL-9/lb 5*o R&

m g"g- *, L L L La G

w - W .- .-

g EE5 w-mmm m mm mm .

mmm m mm

f. f y A An' A n'n' AA n' u n A n' n'
  • i 05. ddd - 'd* *d ~

v *d * ~ d*

E E 77 7 7 777 g:

" g{ "m*= cr

  • er *E ac crE '; ~
  • ma 7 7

% *= E EE

~El E:

I. $

II P @ oder o.

E s
'

. E

-I m x t- k- k

.E' "Eg: -

gj eve T E"yfs i E' e mE EE mee e mE e .

g i al -

b E

al i t t 7 i

g!

l 3- 3 f, i 1

  • 3 5"l~ u-Suu :* lu"3 c 6
u e w' T E 3 E13 t 2 E S U
  • 53i;i "

Eu' SnE3" kst. g 5 {c sE .h g-m]%Ct:- -

g" -ft - E gt w yg **.* : cTt["id.e

. E

- - m. n r s gi m m3::.

t .t gas"

'E*:

W M w E

g ka";*sthA**j a g *R'*r-

~

k"%'t's?

- =

g e m g i T kt_.Z "g.y f5 5rj - - }.p}:

a j"t.u- jE

~ a a . gs .

m

. . m -lH..i

~

$ i Ad4 i J ak i Yn i

2:

s s n

.s -

Ad 4 i s' U ai d

GIUUC GULF - UNIT 2 3/4 3 35 Amencuent he. 20;._,

9 - -- - - .

NL-4l/fo

_ TABLE 4.3.3.1 1 (Continued)

_ EMERGENCY CORE COOLING SYSTEM ACTUATION INSTRUMENT '

SURVEILLANCE REQUIREMENTS

_ NOTATION Notequal or required to 135 to psig.

be OPERABLE when reactor steam done pressure is less than The injection function of Drywell Pressure - High and Manual Initiation arethe on notwide required rangeto be OPERABLE with indi .ated reactor vessel water level instrument sure less thangreater 600 psig. than Level 8 setpoint c incident with the reactor pres-Applicable 3.5.2 or 3.5.3. when the system is required to be OPERABLE per Specification (a) Calibrate Required when ESF equipment is required to_.be OPERAll' (b) trip unit at least once per,3r[ days.

Manual during shutdown. switches shall be tested at least once per 18 months initiation All other circuitry associated with manual initiation shall receive a CHANNEL FUNCTIONAL TEST at least once per)1{ days as a -

(c) DELETED partofcircuitryrequiredtobetestedforautomaticsystemactuation.h (d) DELETED-(e) Functional Testing of Time Delay Not Required GRAND GULF-UNii 1 3/4 3-36 Amendment No. 21 3

.- -w w , , - - - , - _ ,- . - ,~v+- , w y ..w -----

.t o

$ TABLE 4.3.6-1

% t i.

o c

CONTROL ROD BLOCK INSTRUMENTATION SURVEILLANCE REQUIREMENTS 7_c >

$c CHANNEL CHANNEL FUNCTIONAL CHANNEL OPERATIONAL 5 CONDITIONS FOR WHICH 3 TRIP FUNCTION CHECK TFST- CALIBRATION (a) SURVEILLANCE REQUIRED 1

[. 1. ROD PAIIERN CONTROL SYSTEM S/U ID) ,

a. Low Power Setpoint NA_ q Q 1, 2
b. High Power Setpoint: NA S/U(b) , Q 1** I
2. APRM l
a. Flow Biased Neutron Flux-Upscale NA ,V WI )f9) , SA 1 l
b. Inoperative- NA S/U,/ [k; Nfh) , SA I* 2* 5  :
c. Downscale NA W

, y d. Neutron Flux _- Upscale, Startup NA g/U(b)

S , Q 1

2, 5 t

3 y 3. SOURCE RANGE MONITORS

! E a. Detector not' full in NA S/U,W NA 2, 5 I b. Upscale .NA S/U,W Q 2, 5 i i

c. Inoperative NA S/U,W NA 2, 5 t
d. Downscale NA S/U,W Q 2, 5
4. INTERMEDIATE RANGE MONITORS j a. Detector not full in MA S/U,W NA 2, 5 i b. Upscale. NA S/U,W Q 2, 5  !
c. Inoperative NA S/U,W NA 2, S ,

2'

d. Downscale- NA S/U,W Q 2, 5 '

, g 5. SCRAM DISCHARGE VOLUME l @ a. Water Level-High

^

MA frh R 1, 2, 5* l

.y 6. REACTOR COOLANT SYSTEM RECIRCULATION FLOW '

i [.

'O

~

a. Upscale NA

)(h Q l l

1 7. REACTOR MODE SWITCH SHUTDOWN '

l $ POSIIION NA R NA 3, 4  !

4 r

m.-Wio i

3/4.3 INSTRUMENTATION >

BASES' 3/4.3.1 REACTOR PROTECTION SYSTEM INSTRUMENTATION The reactor protection system automatically initiates a teactor scram to:

a. Preserve the integrity of the fuel cladding,
b. Preserve the integrity of the reactor coolant system,
c. Minimize the energy which must be absorbed following a loss of-coolant and
d. accident}nadvertentcriticality.

Prevent

  • This specification provides the Haiting conditions for operati% r.ecessary to preserve the ability of the system to perform its intendeo function even during periods when instrument channels may be out of service because of main-tenance. When necessary, one channel may be made inoperable for brief intervals to conduct required surveillance.

The reactor protection system is made up of two independent trip systems.

-Tnere are usually four channels to monitor each_ parameter with two channels in each trip system.- The outputs of the channels in a trip system are combined in a logic so that eithet.' channel will trip that trip system. The tripping of both trip systems will produce a reactor scram. Specified surveillance intervals and surveillance and-maintenance outage times have been determined in ,

accordance with NEDC-30851P, " Technical Specification Improvement Analyses for BWR Reactor Prote: tion System," as approved by the NRC and documented in the SER (letter T. A. Pickens from A. Thadant dated July 15,1987). The bases for the trip settings of the RPS are discussed in the bases for Specification 2.2.1.

.The measurement of response time at the specified frequencies provides assurance that the protective functions associated with each channel tre com-pleted within-the time limit assumed in the accident analysis. No credit wai, taken for those channels with response times indicated as not applicable. '

Response time may be demonstrated by any series of sequential, overlapping or total channel test measurement, provided such tests demonstrate the total channel response time as defined. Sensor response time verification may be demonstrated by either. (1).inplace, onsite or offsite test measurements, or  ;

(2) utilizing replacement sensors with certified response times.  ;

\

3/4.3.2 ' ISOLATION ACTUATION INSTRUMENTATION This specification ensures the effectiveness of the instrumentation used to mitigate the consequences of accidents by prescribing the OPERABILITY trip setpoints cnd response times-for isolation of the reactor systems. When neces-sary, one enannel may be inoperable for brief' intervals to conduct required -

surveillance. Some of the trip settings may have tolerances explicitly stated where both the high and low values are critical and may have a substantial effect on safety. Negative barometric pressure fluctuations are accounted for  ;

in the trip setpoints and allowable values specified for drywell pressure-high.

The setpoints of other instrumentation, where only the high or low end of the setting have a direct bearing'on safety, are established at a level away from the normal operating range to prevent inadvertent actuation of the systems involved. i hn6c.

l. GRAND GULF-UNIT 1 B 3/4 3-1 Amendment No. 67; -

1

,,_,,___-,,_._..w..+,..,,,,,, ,

,,.,,,-,_,_m.. ...m.._,.__

NL-91/10 Insort_To_Page B.3/_4_3-1 Specified surveillanen interval 8 and nurveillanen and maintennnce outagn times have boon determined in accordanen with: (1) NEDC-30851p-A, Supplement 2. "Tnchnical Specification Improvement Analyste for liWR Isolation Instrumenitntion Common ta EPS and ECCS Instrumentation" as approved by thn NRC nnd documented in the NRC Snfaty Evaluation Report p (letter to D. N. Grace from C E. Rossi dated January 6, 1989) and (2) 4 NEDC-31677P-A, " Technical Specification improvement Analysis for llWR '

Isolation Actunt lots itistrumentation" as approved by tha NRC and documented in the NRC Snicty Eva)untion Report (letter to S. D. Floyd from C. E. Ronni dated Juno 18, !990).

G9105101/SNLICFLR ,. .____ _ . . . . . . .

NL 91/10 INSTRUMENTATION BASES l

ISOLATION ACTUATION INiTRUMENTATION,(continued)

Except for the MSIVs, the safety analysis dow ne address individual sensor response times or the response times of the logM .y.tMs to which the sensors are connected. For 0.C. operated valves, a 3 seco M a m is assumed before the valve starts to move. For A.C. operated valves, it h w 9med that the A.C. power supply is lost and is restored by startup of the emei. 'cy A sel .

generators. In this event, a time of 10 seconds is assumed before the .e starts to move. In addition to the pipe break, the failure of the D.C. l wA '

valve is assumed; thus the signal delay (sensor response) is concurrent 1h the 10 second diesel startup. The safety analysis considers an allowable invi v. ort loss in each case which in turn determines the valve speed in conjunction vith the 10 second delay. It follows that checking the valve speeds and the 10 second time for emergency power establishment will establish the respo is e time for the isolation functions. However, to enhance overall system rella-bility and to monitor ir.strument channel response time trends, tha isolat hn actuation instrumentation response time shall be measured and recorded as a part of the ISOLATION SYSTEM RESPONSE TIME.

Operation with a trip set less conservative than its Trip Setpoint but within its specified Allowable Value is acceptable on the basis that the difference between each Trip Setpoint and the Allowable Value is equal to or greater than the drift allowance assumed for each trip in the safety analyses.

3/4.3.3 EMERGENJYCORECOOLINGSYSTEMACTUATIONINSTRUMENTATION The emergency core cooling system actuation instrumentation is provided '

to initiate actions to mitigate the consequences of accidents that are beyond the ability of the operator to control. This spec,fication provides the OPERABILITY requirements, trip setpoints and response times that will ensure effectiveness of the systems to provide the design protection. Negative baro-metric pressure fluctuations are accounted for in the trip setpoints and allow-Lgyt able values specified for drywell pressure-high. Although the instruments are listed by system, in some cases the same instrument may be used to send the actuation signal to more than one systam at the same time.

Operation with a trip set less contarvative than its Trip Setpoint but within its specified Allowable Value is acceptable on the basis that the differ'ance between each Trip Setpoint and the Allowable Value is equal to or greatt.r than the drift allowance assumed for each trip in the safety analyses.

3/4.3.4 RECIRCULATION PUMP TRIP ACTUATION INSTRUMENTATION The anticipated transient without scram recirculation pump trip (ATVS-RPT) system provides a means of limiting the consequences of the unlikely occurrer.ce of a failure to scram during an anticipated transient. The response of the plant to this postulated event has been evaluated in General Electric Company

, report NEDC-32408 dated March 1987. The results of the analysis show that the Grand Gulf ATWS-RPT design,provides adequate protection for these events in which the normal scram patns fail.

l The ATWS-RPT provides fully redundant trip of the recirculation pump motors so that the pumps coast down to zero speed. This trip function recuces core flow creating steam voids in the core, thereby decreasing power generation i

and limiting any power or pressure excursions. The Grand Gulf ATWS-RPT de ign provides compliance with the requirements of the NRC ATVS Rule 10CFR50.62.

GRAND GULF-UNIT 1 8 3/4 3-2 Amendment No. 67)

q-NL-91/10 Inser.t To Pare B 3/_4J._2 Specified surveillance-intervals and surveillance and maintenance outage times have been determined in accordance with NEDC-30936P-A, Parts 1 and 2, " Technical Specification Improvement Methodology (With Demonstration for BWR ECCS Actuation Instrumentation)" as approved b/ the NRC and documented in the NRC Safety Evaluation Reports (letter to D. N. Grace from A. C. Thadani dated December 9, 1938 (Part 1) cnd-letter to D. N. Grace from C. E. Rossi dated December 9, 1988 (Part 2)).

G9105101/SNLICFLR - 27

. . . - -- .- -. .- .-. ~. - - . . - . ~ -- -- - -. ..

NL-91do 7 INSTRUMENTATION BASES RECIRCULATION PUMP T*** ACTUATION INSTRUMENTATION (Continued)

Operation with a trip set less conservative than its Trip Setpoint but within its specified Allowable Value is acceptable on the basis that the

- difference between each Trip Setpoint and the Allowable Value is equal to or greater then the drift allowance assumed for each trip in the safety analyses.

3/4.3.5 REACTOR CORE ISOLATION COOLING SYSTEM ACTUATION INSTRUMENTATION The reactor core isolation cooling system actuation instrumentation is

- provided to initiate actions to assure adequate core cooling in the event of reactor isolation from its primary heat sink and the loss of feedwater flow to-the reactor vessel without providing actuation of any of the emergency core cooling equipment.

Operation with a trip set less conservative than its Trip Setpoint but within its specified Allowable Value is acceptable on the basis that the difference between each Trip Setpoint and the Allowable Value is equal to or greater than the drift allowance assumed for each trip in the. safety analyses.

3/4.3.6 CONTROL ROD BLOCK INSTRUMENTATION The control rod block functions are provided consistent.with the require-ments of the specifications in Section 3/4.1.4, Control Rod Program Controls and Section 3/4.2 Power Distribution Limits. The trip logic is arranged so that a trip in any-one of the inputs will results in a control rod block.

The OPERABILITY of the control rod block instrumentation in OPERATIONAL CONDITION 5 is to provide diversity of rod block protection to the one-rod-out-interlock. -

d J

9 GRAND GULF-UNIT 1 B 3/4 3-3a Amendment No. 41).-

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

NL-91/10 In5ArLTo Page B 3/1.3-pa Specified surveillanco intervals have been determined in accordance with NEDC-30851P-A, Supplement 1, " Technical Specification. Improvement Analysis for BWR Control Rod Block Instrumentation" as approved by the NRC and documented in the NRC Safety Evaluation Report (letter to D. N. Grace from C. E. Rossi cated September 22, 1988).

l l

l l

l G9105101/SNLICFLR '8 l--

I:

l

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

Retrieved from "https://kanterella.com/w/index.php?title=ML20077H088&oldid=2764689"