ML20064C096

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Proposed Tech Specs,Reflecting Relocation of Response Time Limits to Usar,Per GL 93-08
ML20064C096
Person / Time
Site: River Bend Entergy icon.png
Issue date: 03/03/1994
From:
ENTERGY OPERATIONS, INC.
To:
Shared Package
ML20064C091 List:
References
GL-93-08, GL-93-8, NUDOCS 9403090149
Download: ML20064C096 (10)
v • d • e


Text

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INDEX LIST OF TABLES TABLE TITLE PAGE 1.1 Surveillance Frequency Notation..................... 1-10 1.2 Operational Conditions.............................. 1-11 2.2.1-1 Reactor Protection System Instrumentation Setpoints. 2-4 1

3.3.1-1 Reactor Protection System Instrumentation........... 3/4 3-2 .

(D ^'

3.3.1-2 (pELGTGO::: r Pr:tectier Sy ter R::per.:: 'jg[).......... 3/4 3-6 ,

4. 3.1.1- 1 Reactor Protection System Instrumentation Surveillance Requirements........... ......... ..... 3/4 3-7 j 3.3.2-1 Isolation Actuation Instrumentation................. 3/4 3-12 .

3.3.2-2 e Actuation Instrumentation Setpoints...... 3/4 3-19 ELE TE b 3.3.2-3 J::1: tier Sy:ter In:trument: tier R::;cc:: 7' e, .... 3/4 3-24 4.3.2 1-1 Isolation Actuation Instrumentation Surveillance

Requirements........................ ............... 3/4 3-26 ,

3.3.3-1 Emergency Core Cooling System Actuation .

Instrumentation.... .................. ........ .... 3/4 3-31

, 3.3.3-2 Emergency Core Cooling System Actuation ,

Instrumentation Setpoints......................... . 3/4 3-36

( OrteTED '

( Er r;:n:3 C:r: C::?'n; Sy:t - 9::;:::: ::)....... 3/4 3-40 3.3.3-3 4.3.3.1-1 Emergency Core Cooling System Actuation Instrumentation Surveillance Requirements........ .. 3/4 3-41 3.3.4.1-1 ATWS Recirculation Pump Trip System Instrumentation. 3/4 3-45

3. 3. 4.1-2 ATWS Recirculation Pump Trip System Instrumentation Setpoints........................................... 3/4 3-46 r

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RIVER BEND - UNIT 1 xxiii Amendment No.12.

9403090149 940303 s PDR ADOCK 05000458 P PDR 44 ,

4 ..+.,-m ---  :- , _ y ,

3/4.3 INSTRUMENTATION 3/4.3.1 REACTOR PROTECTION SYSTEM INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.3.1 As a minimum, the reactor protection system instrumentation channels shown in Table 3.3.1-1 shall be OPERABLifw kh th: REACTORPROTECTIONSY5TEiO

@E{0ZCTI": a; shgr.IT. .,..,.. g APPLICABILITY: As shown in Table 3.3.1-1.

ACTION:

a. With the number of OPERABLE channels less than required by the Mini-mum OPERABLE Channels per Trip System requirement for one trip system, place the inoperable channel (s) and/or that trip system in the tripped condition" within one hour.
b. With the number of OPERABLE channels less than required by the Minimum OPERABLE Channels per Trip System requirement for both trip systems, place at least one trip system ** in the tripped condition within one hour and take the ACTION required by Table 3.3.1-1.

SURVEILLANCE REQUIREMENTS 4.3.1.1 Each reactor protection system instrumentation channel shall be demon-strated 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 4.3.1.1-1.

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

required 4.3.1.3 The REACTOR PROTECTION SYSTEM RESPONSE TIME of eachtreactor trip functional unit 6 ~ - in T 2 11 2.3 1 j 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 that all chan,nels are tested at least once every N times 18 months where N is the total nurber of, radundant cha_nnels in a_ speciff reactor trip system. l/ A)edre, de& fed dre. eiesp+ b 2

r re > c.ne bme bes%3 .

"An inoperable channel need not be placed in The tripped con on where t is the Trip Function to occur. In these cases, the inoperable channel would shall because,lored res to OPERABLE status within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> or the ACTION requ Table 3.3.1-1 for that Trip Function shall be taken.

    • The trip system need not be placed in the tripped condition if this would cause the Trip Function to occur. When a trip system can be placed in the tripped condition without causing the Trip Function to occur, place the trip  ;

system with the most inoperable channels in the tripped condition; if both I systems have the same number of inoperable channels, place either trip system in the tripped condition. The requirement to place a trip system in the tripped condition does not apply to Functional Units 6 and 10 of Table 3.3.1-1.

      • Logic System Functional Test period may be extended as identified by note 'p' on Table 4.3.1.1-1.

RIVER BEND - UNIT 1 3/4 3-1 Amendment No.S. 47

  • l

3[ TABLE 3.3.1-2 REACTOR. PROTECTION SYSTEM RESPONSE TIES

  • 5 RESPONSE TINE FUNCTIONA L; NIT (Seconds) s / M ')'

Q 1. fintermediate Range IIenitors/  : j' E s j/ a. NeutronFlux-HigV NA '

LF

b. Inoperative NA ',

/2. Average Power a.

/ ltor*:

Neutron Flux High, Setdown f ,H W

1 t

NA / -

b.

c.

Flow Blased' Simulated Thermal Power - H gh Neutron F)'ux - High

<0.09,** r $

70.p9

d. Inoperafive < .

s- j 0

t' 3. Reactor Vps/sel Steam Dome Pressure - High 0.35 i Y

-4.

S.

ReactorfWessel Water Level - Low, Ley 41 3 Level 8 /

71.05 71.05 >T' F-l

6. Main, steam Line Isolation Valve / Reactor Vessel Water 70.09 Level - High,flosure "
7. Maid Steam Line Radiation - High RA lL '
8. 11 Pressure - High / NA (L
9. cram Discharge Volume Water L,evel - High 'P
a. Level Transmitter NA 7

/. b. Float Switches NA

0. Turbine Stop Valve - Closure L

<0.06

11. Turbine Control Valve' Fast Closure Valve Trip System Oil Pressure - Lo/ <0.07#
12. Reactor Mode Switcli Shutdown Position HA k 13. Manual Scram / NA

/ -

-S

  • Neutron detectors are exempt from responsej t me testing. Response time s 1 be measured z from the detector output or from the input of the first electronic c nt in the channel.

F **Not including simulated thermal power tjee constant specified in the C0J . J, l g #MeasuredfromstartofturbinecontroJ/'valvefastclosure. / _

. . - - .- - -- -----.----D

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INSTRUMENTATION 3/4.3.2 ISOLATION ACTUATION INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.3.2 The isolation actuation instrumentation channels shown in Table 3.3.2-1 shall be OPERABLE with their trip setpoints set consistent with the value tsho n in the Trio Setpoint column of Table 3.3.2-fiETURCOLATION f5ff[RESPOR6G (TIMEe5 3 hwr, i r. lebl e 3. 3. 2-3,rf APPLICABILITY: As shown in Table 3.3.2-1.

ACTION:

a. With an isolation actuation instrumentation channel trip setpoint 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.

l b. With the number of OPERABLE channels less than required by the Minimum OPERABLE Channels per Trip System requirement for one trip system, place the inoperable channel (s) and/or that trip system in the tripped condition

  • within one hour.
c. With the number of OPERABLE channels less than required by the Minimum OPERABLE Channels per Trip System requirement for both trip systems, place at least one trip system ** in the tripped condition within one hour and take the ACTION required by Table 3.3.2-1.
  • An inoperable channel need not be placed in the tripped condition where this would cause the Trip Function to occur. In these cases, the inoperable channel shall be restored to OPERABLE status within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> or the ACTION required by Table 3.3.2-yorthatTripFunctionshallbetaken.
    • The trip system need not be placed in the tripped condition if this would cause the Trip Function to occur. When a trip system can be placed in the tripped condition without causing the Trip Function to occur, place the trip system with the most inoperable channels in the tripped condition; if both systems have the same number of inoperable channels, place either trip system in the tripped condition.

l RIVER BEND - UNIT 1 3/4 3-10 Amendment No. 47 1

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INSTRLMENTATION 1 l

SURVEILLANCE REQUIREMENTS  ;

4.3.2.1- Each isolation' actuation instrumentation channel shall be' demonstrated-OPERA 8LE by the performance of the CHANNEL CHECK, CHANNEL FUNCTIONAL TEST and f.HANNEL CALIBRATION operations for the OPERATIONAL CONDITIONS and at the frequencies shown in Table 4.3.2.1-1.

4.3.2.2 LOGIC SYSTEN FUNCTIONAL TESTS and simulated automatic operation of all channels shall be performed at least once per 18 gop hs *

,. (required ) ..

4.3.2._3 The ISOLATION SYSTEM RESPONSE TINE of eachfisolation trip function (it.= 5 Table- 3.3.2-O shall be demonstrated to be within its limit at least onte per la.nontns. Each test shall include at least one channel per trip system such 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 system.

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[

  • Logic System Functional Testing period may be extended as identified by notes .

C and D on Table 4.3.2.1-1.

RIVER BEND - UNIT 1 3/4 3-11 Amendment No. 8

. 71 l J.J. 2 -( bco Lee- delefM

[ TABLE 3.3.2-3

/

/ / /

ISOLATION SYSTEM INSTRUMENTATION RESPONSE /fIME TR FUNCTION ESPONSE TIME (Seconds)#

. PRIMARY CONTAINMENT ISOLATION ,

a. Reactor Vess Water Level - Low Low Leve 2 < 10(a)
b. Drywell Predsure - High 7 10(a) j
c. Containme f. Purge Isolation Radiation - HighO) RA
2. MAIN STEAM VINE ISOLATION ,
a. React r Vessel Water Level - Low L w Low b.

Le' vel 1 Ma/n Steam Line Radiation - Hi tb /) < 1.0 */< 10(I'**

I 1.0 */7 1,0((a)..

c. $inSteamLinePressure-Lo I1.0*/h10(a),,
d. ain Steam Line Flow - High 7 0.5 */ 10 a) ,
e. Condenser Vacuum - Low RA f Main Steam Line Tunnel Temperature - High NA

. Main Steam Line Tunnel # Temperature - High NA

h. Main Steam Line Area T 'perature - High (Turbine Bldg) NA

/.SECONDARYCONTAINMENTIS

a. Reactor Vessel Wa r Level - Low Low Level 2 < 10(a)
b. Drywell Pressurp'- High 7 10(a) ,
c. Fuel Building Ventilation Exhaust Radiation - High( RA ,
d. Reactor Building Annulus Ventilatio Exhaust Radiation - High 5b) NA ,
4. REACTOR WATE CLEANUP SYSTEM ISOLATION
a. A Flo - High < 10(a)N
b. A F1 Timer RA
c. Eqy pment Area Temperature - High NA
d. E(uipment Area a Temperature - High NA ,) l
e. eactor Vessel Water Level - Low Low evel 2 <

- l  !

f. Main Steam Line Tunnel Ambient -

Temperature - High A f

g. Main Steam Line Tunnel a Tempera,ure - High NA J
h. SLCS Initiation / NA l
f. REACTOR CORE ISOLATION COOLING S TEM ISOLATION
a. RCIC Steam Line Flow - H gh < 10(*) #
b. RCIC Steam Line Flow-Hig Timer NA
c. RCIC Steam Supply Pressure - Low < 10(,)
d. fDiaphrage Pressure - gh NA

~

e. RCIC TurbineRoom' RCIC Equipment Exhaust, Ambient Temperatureigh NA
f. RCIC Equipment Room a Temperature - Hig NA
g. Main Steam Line , Tunnel Ambient Temperature - High NA 4
h. Main Steam Line' Tunnel a Temperatu e/ High.

RIVER BEND - UNIT 1 3/4 3-24

le 3 3.2 3 Nas ben Oebebek. --

6 / TABLE 3.3.2-3 (Continued)

ISOLITIONSYSTEMINSTRUMENTATIONRESPONSETIME RESPONSE (IME (Seconds)#

TRIP FUNCTIOh am Line Tunnel Temperature Timer NA

i. Main NA
j. RHR Equipment Room Ambient Temperature - High NA k RH8' Equipment Room a Temperature - High M/RCIC Steam Line Flow - High NA NA eywell Pressure - High ,

NA n.f rianual Initiation /

/

/ ,

6. ,R R SYSTEM ISOLATION ,-

e

, a. RHREquirwntAreaAmbiMtTemperature-High NA

/ b. RHR Equ' 't Area a Temperature - High NA

< 10(a)

[ c. Reactor i Water /l evel - Low Level 3 -

d. Reactor . w ei Water Level - Low Low Low Level 1 / ' ~

< 10 )/

e. Reactor Vessel (RHR Cut-in Permissive) NA /

Pressure - High

f. Drywell Pressure - High g/

/

/ /NA

7. MANUAL INITIATION

/

(a) Isolatiop tem instrumentation response time specif d includes the diesel Senerato'r starting and sequence loading delays.

/

iation detectors are exempt from response tim testing. Response time c

,cil be measured from detector output or the iriput of the first electro component in the channel.

ime for MSIVs only. No esel

'* Isolation system instrumentation response generator delays assumed.

    • Isolation system instrumentation res ernse time for associated alves except MSIVs.
  1. Isolatfor system instrumentation / response time specified or the Trip Function actuating each valve gfoup shall be added to i lation time shown in Tables 3.6.4-1 and 3.6.5.3d for valves in each va e group to obtain l

i ISOLATION SYSTEM RESPONSE T HE for each valve.

    1. Time delay of 45-47 secon s.

l

      1. Time delay of 3-13 sedonds. i l /

l RIVER BEND - UNIT 1 3/4 3-25 l

e

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\. INSTRUMENTATION 3/4.3.3 EMERGENCY CORE COOLING SYSTEM ACTUATION INSTRUMENTATION LIMITING CONDITION FOR OPERATION i

3.3.3 The emergency core cooling system (ECCS) actuation instrumentation channels shown in Table 3.3.3-1 shall be OPERABLE with their trip setpoints set _ consistent with _the values shown in the Trio Setpoint column of Table 3 J.3 (eg iu, CMCROCNCY CORC C00;.!NO SYSTEM RC;"0N APPLICABILITY: As shown in Table 3.3.3-1.

ACTION:

a. With an ECCS actuation instrumentation channel trip setpoint less conservative than the value shown in the Allowable Values column of Table 3.3.3-2, declare the channel inoperable until the channel is restored to OPERABLE status with its trip setpoint adjusted consistent with the Trip Setpoint value.
b. With one or more ECCS actuation instrumentation channels inoperable, take the ACTION required by Table 3.3.3-1.
c. With either ADS trip system "A" or "B" inoperable, restore the inoperable trip system to OPERABLE status:  ;

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1. Within 7 days, provided that the HPCS and RCIC systems are OPERABLE, or
2. Within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />, provided either the HPCS or the RCIC system is inoperable.

Otherwise, 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 i reduce reactor steam dome pressure to less than or equal to 100 psig within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

SURVEILLANCE REQUIREMENTS I 4.3.3.1 Each ECCS actuation instrumentation channel shall.be demonstrated OPERA 8LE by the performance of the CHANNEL CHECK, CHANNEL FUNCTIONAL TEST and CHANNEL CALIBRATION operations for the OPERATIONAL CONDITIONS and at the 4 frequencies shown in Table 4.3.3.1-1. .

4.3.3.2 LOGIC SYSTEM FUNCTIONAL TESTS and simulated automatg operation of. .

all channels shall be performed at least once per 18 months l.

" Logic System Functional and ECCS Response time testing period may be ,

extended as identified by note C on Table 4.3.3.1-1. ,

F RIVER BEND - UNIT 1 _3/4 3-30 Amendment No. 9 l

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. INSTRUMENTATION 3 '4. 3. 3 EMERGENCY CORE COOLING SYSTEM ACTUATION INSTRUMENTATION LIMITING CONDITION FOR OPERATION 4.3.3.3 At least once per 18 months ##,theECCSRESPONSETIMEofeachhCSt p function Eh:un in T:b!: 2.3.3-3)shall be demonstrated to be within the limit.

Eachtestshallincludeatleastonechannelpertripsys)gesuchthatall channels are tested at least once every N times 18 months where N is the total l number of redundant channels in a specific ECCS trip system.

  • I I

l I

    1. Logic Systens Functional and ECCS Response time testing period may be extended as identified by note C on Table 4.3.3.1-1.

i i i RIVER BEND - UNIT 1 3/4 3-30a Amendment No. 9

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TABLE 3.3.3-3 /

/ EMERGENCY /f E COOLING SYSTEM RESP _0 SE TIMES

/

/ / /

ECCS RES(ONSETIME(Seconds) fl. LOW PRESSURE C0 SPRAY SYSTEN 5 37 2.

LOW PRESSURE 00LANT INJECTION MODE OF RHR SYS EM

a. Pump / A and B
b. Pu ' C

< 37 537

3. AUTO IC DEPRESSURIZATION STEM NA 4

HIG PRESSURE CORE SPRAY SYSTEM 27 COSS OF POWER NA 3.3,j-3 een CPI *k' ' -

I RIVER BENO - UNIT 1 3/4 3-40

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