U-601871, Proposed Tech Specs Re Reactor Protection Sys Instrumentation,Containment & Reactor Vessel Isolation Control Sys & ECCS Instrumentation Surveillance Requirements

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Proposed Tech Specs Re Reactor Protection Sys Instrumentation,Containment & Reactor Vessel Isolation Control Sys & ECCS Instrumentation Surveillance Requirements
ML20078A062
Person / Time
Site: Clinton Constellation icon.png
Issue date: 09/20/1991
From:
ILLINOIS POWER CO.
To:
Shared Package
ML20078A058 List:
References
U-601871, NUDOCS 9109300200
Download: ML20078A062 (41)
v • d • e


Text

At t achment 3 U-bnl871 LS-68-047 Page 1 of 42 l

3/4,3 INSTRUMEgATION 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 OPERABLE

  • with the REACTOR PROTECT RESPONSE TIME as shown in Table 3.3.1-2.

APPLICABILITY: As shown in Table 3.3.1-1.

ACTION:

a. For all functional units of Table 3.3.1-1 other than Reactor Mode Switch Shutdown Position.
1. With one of the four channels required for any Trip Function inoper-able, operation may continue provided the inoperable Thechannel is of provisions placed in the tripped condition within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />.

Specification 3.0,4 are not applicable.

2. With two of the four channels required for any Trip Fun tien facrg._ ne-49ue-able, place one channel in the tripped condition withi =

provided no tripped channel for that Trip Function already~ exists.-

The provisions of Specification 3.0.4 are not applicable.

3. With three of the four channels required for any Trip Function inoperable, take the ACTION required by Table 3.3.1-1.
b. For Reactor Mode Switch Shutdown Position take the ACTION as shown i Table 3.3.1-1.

EVEILLANCEREQUIREMENTS 4.3.1.1 Each reactor protection system instrumentation channel shall be demon-strated OPERABLE by the performance of the CHANNEL CHECK CHANNEL FUNCTIONA 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 Reactor SYSTEM FUNCTIONAL TESTS shall be performed at least once per 18 protection system divisional logic and portions of the channel months.

coincident logic shall be manually tested independent of the SELF TEST SYSTEM ch that a11 trip functions are tested at least during each refueling outage l once every four fuel cycles -**-

l "A channel may be placed in an inoperable status for up to e hours for required surveillance provided at least two OPERABLE channels are monitoring that e -

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b TABLE 4.3.1.1-1 (Continued) .

REACTOR PROTECTION SYSTEM llI51Rt ,itiiAT10?I SursvEf ttAfiCE ffEQtliRfMENTS

! n C

x CPERATIGHAL Cl!HaiEL y

DIA! CIEL CCHDITIG!!5 IN MilCil CitAfiNEL FLf!ICTICHAL 1EST I

CAtt0 RAT 10!a*) SURVEfttANCE :EqulRio CIIECK flmCT10ttAt U1:11

9. Scram Olscharge volume Water
  1. tevel - tilgte 5 R(9} 1. 2. 5( }
a. Level Transmitter 1, 2. 5 I}

IIA Q R ti. Float Switches M"} R("} }  !

10. Turbine Step Valve - Closure NA
11. Turbine Control Valve Fast Cicture Valve Trip Systes Oil R(m) 1 w Pressure - tow IL*. (St -HAr5) 1 m 12. Reactor Hode Switch  !!A R tlA 1.2,3.4,S a Shutd wn Positicn f4A IIA 1.2.3.4.5 f
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Attachment 3

. U-601871 LS-68-042 1 Aut t 4. 3.1. P1 (Continue 25% of RATED TilERMAL POWER. Adjust the APRM channel if the absolute diTrerence is greater than 2% of RA1ED TilERMAL POWER.

(c) This calibration shall consist of a setpoint verification of the Neutron Flux-liigh and the Flow Biased Simulated Thermal Power-liigh trip functions.

The Flow Biased Simulated Thermal-liigh trip function is verified using a calibrated flow signal.

t (f) The LPRMs shall be calibrated at least once.per 1000 ef fective full power hours (EFPil) using the TIP system.

92.

(g) Calibrate the analog trip module at least once pc -3+ days.

(h) Deleted.

(i) This calibration shall consist of verifying the 610.6 second simulated thermal power, time const. ant.

(j) This function is not required to be OPERABLE when the reactor pressure vessel head is removed per Specification 3.10.1.

(k) With any control rod withdrawn. Not applicable to control rods removed per Specification 3.9.10.1 or 3.9.10.2.

(1). This function is not required to be OPERABLE wht:n DRYWELL INTEGRITY is not required to be OPERA 3LE per Special Test Exception 3.10.1.

(m) The CHANNEL FUNCTIONAL TEST and CilANNEL CAllBRATION shall include the turbine first stage pressure instruments.

l l

l l

CLINTON - UNIT 1 3/4 3-10 Amendment No. 30

4 At t ac htwnt 3 U 601671 LS68-042 l'a r c $ of 42 INSTRUMENTAT10N 39,.3.2 CONTAM"DIT PD REACTOR VESSEL ISOL ATION CONTRC' SYSTEM LIMITING CONDIT]ON FOR OPERATION _

3.3.2 The contaircent and reactor vessel isolation control system (CRVICS) channels shown in Table 3.3.2-1 shall be OPERABLE" with their tr'ip setpoints set consistent with the values shown 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 a CRVICS channel trip setpoint less conservative than the value shown in the Allowable Value column of Table 3.2.2-2, declare the channel inoperable until the channel is restored to OPERABLE status with its trip setpoint adjusted consistent with the Trip Setpoint value.
6. For CRVICS Main Steam Line Isolation Trip functions:
1. With one of the four channels required for any Trip Function inopera-ble, operation may continue provided the inoperable charinel is placed in the tripped condition within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />. The provisions of Speci-fication 3.0.4 are not applicable.
2. With two of the four channels required for any Trip Function _inopera ble, place one cnannel in the tripped condition within fene-h W 5 h -

provided no tripped channel for that Trip Function already exists.

The provisions of Specification 3.0.4 are not applicable.

3. With three of the four channels required for any Trip Function inoperable, take the ACTION required by Table 3.3.2-1.
c. For other CRVICS isolation Trip functions:
1. W!th 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 M 9 The provisions of Specification 3.0.4 are l not applicable. p
  • For CRVICS Main Steam Line Isolation Trip Function, a channel may be placed in an inoperable status for up t f hours for required surveillance provided l at least two OPERABLE channels monitoring that parameter.

For other CRVICS Ist lation Tri unction, a channel may be placed in an in-operable status for up t f- iours for required surveillance provided the l requirements of Table 3.3 -1 are fulfilled.

    • An inoperable channel need not be p'eated in the tripped conditi:.,n where this would cause the Trip Function tn occur. In these cases, the inoperable hours or the ACTION l channel required byshall Tablebe restored 3.3.2-1 f or that toTrip OPERABLE f unction shastatustaken.

within@ll be CLINTON - UNIT 1 3/4 3-11

Attachment )

o 4

U-601671 LS88-042 f Page 6 of 42 l t

INSTRUMENTATION '

CONTAINHENT AND REACTOR VESSEL ISOLATION CONTROL SYSTEM L1HTTING CONDITION FOR OPERATION (Continued) l 3,3.2 ACTION (Continued):

2. 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 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> and take the ACTION required by Table 3.3.2-1.

SURVEILLANCE REQUIREMENTS - 4.3.2.1 Each CRVICS channel shall be demonstrated OPERABLE by the performance of the-CHANNEL CHECK, CHANNEL FUNCTIONAL TEST and CHANNEL CALIBRATION operation for the OPERATIONAL CONDITIONS and at the frequencies shown in Table 4.3.2.1-1, 4.3.2.2 LOGIC CRVICS SYSTEM FUNCTIONAL TESTS shall be performed at least once per main steam Ifne isolation divisional logic and portions of 18 months.

the channel coincident logic shall be manually tested independent of the SELF TEST SYSTEM during each refueling outage.

Each of the two trip systems or divisions of the CRVICS trip synem logic shall.be siteraately and manually tested independent of the SELF TEST SYSTEM during every other refueling outage.

All manual testing shall be complet h that all trip functions are tested at least once every four fuel cycle 4.3.2.3 The CRVICS RESPONSE TIME of each CRVICS trip function shown in Table 3.3.2-3 sha11 be demonstrated to be 'vithth its limit at least once- per 18 months. Each test-shall inciude at least one logic train tested at least once per_36 months, and one channel per trip function 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 CRVICS trip function.

"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 conditio'n; if both systems have the same number of inoperable channels, place either trip system - - _

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Attachment 3 U 601871

+

1.5-86-042 Pa r.c 7 of 42 1 ABl f 3. 3. ?-i (Cont inned)~

CW I W III51i3i$[Nifli100~

TA8tf N0iA110NS

  1. When handling irradiated f uel in the primary or secondary containment and during CORE AllERATIONS and opet ations with a potential for draining the reactor vessel.
    1. When handling irradiated fuel in the primary contairvoent (building) and during CORE ALTEPA110NS and operations with a potential for draining the reactor vessel.
    • When any turbine stop valve is greater than 95% open or the reactor mode

- switch is in the run position.

t Main steam line isolation trip functions have 2-out-of-4 isolation logic cycept for the main steam line flow - high trip function which has 2-out-of-4 isolation logic for each main steam ifne.

ft See Specification 3.6.4 Tabic 3.6.4-1 for valves which are actuated by these isolation signals.

(a) A channel may be placed in an inoperabic status for op to hours tripped for con-required surveillance without placing the trip system in t dition provided .at least one other OPERABLE channel in the same trip system is monitoring that parameter.

(b) Also actuates the standby gas treatment system.

(c) Ocleted (d) Also trips and isolates the mechanical vacuum pumps.

(c) Isolates RWCU valves 1G33-f 001 and 1G33-F004 only.

(f) Also actuates secondary containment ventilation isolation dampers per Tabic 3.6.6.2-1.

(g) Hanual Switch closes RWCU system inboard isolation valves F001, f028, F053, F040 and outboard isolation valves f004 F039, F034 and f054.

(h) Vacuum breaker isolation valves require RCIC system steam supply pressure low coincident with drysell pressure high for isolation of vacuum breaker isolation valves.

(1) A single manual isolation switch isolates outboard steam supply line isolation valve (f064) and the RCIC pump suction from suppres,sion pool valve (F031) only following a manual or automatic (Reactor vessel Water

! Level 2) RCIC system initiation.

(j) Only actuates secondary containment ventilation isolation dampers ction.per Tabic 3.6.6.2-1. Note it is not applicabic to this Trip (k) A channel may be placed in an inoperabic status for up t e ours trip con-for l required surveillance without placing the trip system in dition provided that the redundant trip system is OPERABLE and monitoring that parameter.

(1) Not required to be OPERABLE when valves IVR002A,0 and IVQ006A,8 are scaled i

closed in accordance with Specification 3.6.4.

Amendment No. 48 CLINTON - UNIT 1 3/4 3-18

- - -.,ww --- --- -- ,- < ww *y- * ~pn ~=

TABLE 4.3.2.1-1 CRVICS INSTRUMENTATION SURVEILLANCE REQUIREMEttTS l 35 E CHANNEL OPERATIONAL

' CHANNEL CONDITIONS IN WHICH CHANNEL FUNCTIONAL CALIBRATION SURVEILLANCE REOUIRED E CHECK TEST TRIP FUNCTI0t{

1. PRIMARY AND SECONDARY CONTAltiMENT ISOLATI0t!

R(b) 1, 2, 3, #

a. Reactor Vessel Water Level - S -W Q Lcw Low, Level 2 j
b. Reactor Vessel Water Level - 1, 2, 3 Low Low, level 2 (ECCS -H- Q R(b)

S Div. I and II)

c. Reactor Vessel Water Level - ID} 1, 2, 3 Low Low, Level 2 (ECCS -W Q R S

Div. III) R ID) 1, 2. 3

w 5 4+- Q I D d. Drywell Pressure - High l R(b)
  • 1, 2, 3
c. Drywell Pressure - High (ECCS S M- Q i

[

  • Div. I and II)

[ g 1,2,3

f. Drywell Pressure - High 5 -H- Q R (ECCS Div. III)
g. Centainees.t Building Fuel Transfer Pool Ventilation S t H-Q R

Plenus Radiation - High 1, 2, .1, #

b. Containment Building Exhaust 5 44-Q R Radiation - High E

o 1. Containnent Building Contin- I / , e>

uous Containment Purga J 5' f'C h (CCP) Exhaust P3diation - S l , 45-Q R 1, 2, 3, #

$3E e High 4 5 if G 1.03 F

,O N tot N

i -

TABLE 4.3.2.1-1 (Continued) ,

n .

C CRVICS INSTRUMENTATION SURVEILLANCE REOUIREMENT' 5 CHANNEL OPERATICNAL e CHANNEL FUNCTIONAL CHANNEL CONDITION 5 IN WICH i

TEST CALIBRATION SURVEILLANCE PE0uiFED ^

CHECK c TRIP FUNCTION i5

1. PRIMARY AND SECONDARY CONTAINMENT ISOLATION (Continued)

] j. Reactor Vessel Water Level- R(b) 1,2,3,#

Low Low Lcw, Level 1 S -H- Q

-H- Q R 1, 2, 3, #

Containment Pressure - High 5 ,

k.

1. Main Steam Line Radiation - -M-Q R 1,2,3 S

High Fuel Building Exhaust }

m. R 1, 2, 3, #

Radiation - High S R NA 1, 2, 3, #

Manual Initiation NA w n. '

j u 2. MAIN STEAM LINE ISOLATION

$ a. Reactor Vessel Water Level - -M- Q R(b) 1.2,3 Low Lcw Lcw, Level 1 5 '

A '

b. Main Steam Line Radiation - R 1, 2, 3 High 5 -M-Q /

I ,

c. Main Steam Line Pressure - , -M-Q k R(b)

S Low

-M- Q R(b) 1, 2, 3

d. Main Steam Line Ficw - High S

'H-Q

- R(b) 2, 3** i S

e. Condenser Vacuus - Lew  ;
f. Main Steam Line Tunnel ) R 1, 2, 3 Temp. - High 5  ;> -M-Q }J
g. Main Steam Line Tunnel j R 1, 2, 3 l

5 -H- Q <

t2 Temp. - High 2? ??

! )

h. Main Steam Line Turbine Bldg. I R 1, 2, 3 5$ $[ [

Tecp. - High S

\-M-Qf [j$[  !

1. Manual Inttistion NA 7 NA 1, 2, 3

-~

3 N t

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TABLE 4.3.2.1-1 (Continued)

S CRVICS INSTRLHENTATION SURVEILLANCE REQUIREMENTS G

g OPERATIO?iAL

= CHANNEL CHANNEL FUNCTIONAL CitGNEL C0fGITICNS IN MIICH c- TEST CALIBRATION SURVEILLANCE RE00TRED TRIP FUNCTION CliECK 3

3. REACTOR VATER CLEAfAl? SYSTEM ISCLATION 7 R 1, 2, 3 [

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' a. a Flow - High S Q-M- ]

Q 1, 2, 3

b. A Flow Ticer NA Q-H-1 i
c. Equipeent Area Temp. - High ,

R 1, 2, 3

1. Purp Rooms - A, B, C $ h Q +)
2. Heat Exchangar Rooms - ' l R 1,2,3 j  ;

East, West S Q -M- I

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' R 1, 2, 3 S 1. Pump Rooms - A, B, C $ Q 4t-y 2. Heat Exchanger Roc =s - l 1, 2, 3 R  ;

! O East, Vest 5 yQ-Nd l

e. Reactor Vessel Vater a R(b) 1, 2, 3, #

i Level - Low Low, tevel 2 S i) G -M-I I

i I f. Main Sten. Line Tunnel Ambiet.t 1, 2, 3 Temp. - High S Q4t i R

g. Main Stea= Line Tunnel j 1,2,3 i

l 5 R

> a Teep. - High ( G -%

NA QM*I NA 1, 2, S*

i

h. SLCS Initi& tion  ;

NA R NA 1, 2, 3, #

i. Manual Initiation i

^

4. MEACTOR CORE ISOLATION COOLING SYSTEM ISCLATION ~EN R(b) 1. 2, 3  %- g g; i RCIC Steam Line Flow - High 5 Q -M- -
a. Y U
b. FCIC Steam Line Flow - High Tieer NA Q+ R I. 2, 3 (( (a?

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C G r p e m w I N u a i e A h o B- B s i b T g V I L s D m l l l l F ,e ,

R A a e e e i Ar A C O e n n n i O r t mgh m n n n l

e u C P s u u u- - n rt r u oi c T T T n i ea e N y ah oH o h e o L gr gh ne ng O l hgR R eg e r i I p xi - e n u t m ap ai T p EH t t nh iH ni ig ir s a a hmhH

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L O n ie pt p mu m m H

m mi r i S E t

E S m a- a . aT p n t n t p I a br ia u, i u e ep e I C e ru us qe q t . t m etsp. l l I h ae ar ee E t l Cg ei S Ts Ep Eh S pg e a Hb HT R

O w e m m S. T ner v u /H Ri e m

C Co Cr Ce Ci I H iT ne n iaiT y n R RA Ra N It IP IT a a a r a H H H R C C C C D M R R R O

I O R R R R M M M T T C C N A . . .

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i TABLE 4.3.2.1-1 (Continued)

hes

= CRVICS INSTEMENTATION SURVEILLANCE REQUIREHENTS E

e CHANNEL OPERATIONAL 25 CHANNEL FUNCTIONAL CHANNEL TRIP FUNCTION CONDITIONS IN WICH

--o CHECK TEST CALIBRATION

" SURVEILLANCE REQilIRED

5. RHR SYSTEM ISOLATION
a. PJIR Heat Exchanger Fooms A, B Ambient Temp. - High 5 i

-M-Q R 1, 2, 3

b. RHR Heat Exchanger Rooms A, B a Temp. - High 5 ,' M- Q '

R 1, 2, 3

c. Reactor Vessel Water Level -

Low, tevel 3 S M-Q j R(b) 1, 2, 3

d. Reactor. Vessel Water Level -

R' Low Low Low, level 1 s 5 44-Q' R(b) 1, 2, 3 u e. Reactor. Vessel (RHR Cut-in g Permissive) Pressure - High 5 Q R(b) t 1,2,3

f. Drywell' Pressure - High 1
1) RHR Test Line S b)
2) Fuel Pool Cooling S [g-M-G R(D)

R I y, p 3 1, 2, 3

g. Manual Initiation NA R NA 1,2,3 l 5 ts15

%18;  ;

?se l

", "R a Ei!

t ,

i 6

- Attachment 3

- U-601871 1 ,

LS-88 042 l'a g e 13 of 42 TABLE 4.3.2.1-1JC3tinued]

CRVICS INSTRUMEt4 TAT 10h SURVEILLANCE REQUIREMENTS TABLE NOTATIONS

  1. When handlir.g irradiated fuel in either the secondary or the primary containment and during CORE ALTERATIONS and operations with a potential for draining the reactor vet.sel.
    1. When handling irradiated fuel in the primary containment (building) and during CORE ALTERATIONS and operations with a potential for draining the reactor vessel.
    • When any turbine step valve is greater than 95% open or the reactnr mode switch it in the run position.

L (a) Each train or logic channel shall be tested at least (very othe -* 1ays.

9L (b) Calibrate the analog trip modules at least once per -M days.

i t

CLINTON - UNIT 1 3/4 .3-32 Amendment No. 44

"" --J- - - - - - - - - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _

At t 4tchmetit 3

' U -(,018 71 1.S-88-042 Page 14 of 42 INSTRUMENTATION 3/4,3.3 EMERCENCY CORE COOLING SYSTEM ACTUATION INSTRUMENT ATION LIMITING CONDITION FOR OPERATION 3.3.3 The emergency core cooling system (ECC', actuation instrumentation channels shown in Table 3.3.3-1 shall be OPExABLE with their trip setpoints set consistent with the values shown in the Trip Setpoint column of Table 3.3.3-2 and with EMERGENCY CORE COOLING SYSTEM RESPONSE TIME as shown in Table 3.3.3-3.

APPLICABILITY: As shown in Table 3.3.3-1.

ACTION:

a. With an ECCS actuation instrumentation channel trip setpoint less conserv-
  • ative than the value shown in the Allowable Value 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 "1" or "2" inoperable, restore the inoperable trip system to OPERABLE status within:
1. 7 days, provided that the HPCS and RCIC syntems are OPERABLE, or
2. 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 RCIC systems are inoperable.

Otherwise, be in at least HOT SHUTDOWN within be next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and reduce reactor steam dome pressure to < 100 psig withir the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

SURVEILLANCE REQUIREMENTS 4.3.3.1 Each ECCS 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 4.3,3.1-1.

4.3.3.2 LOGIC SYSTEM FUNCTIONAL TESTS shall be performed at least once per 18 months. The actuation system logic associated with each of the ECCS divisions shall be manually tested independent of the SELF TEST SYSTEM during alternate refueling outages such that all d isions and all trip functions are tested at least once every four fuel cycles 4.3.3.3 The ECCS RESPONSE TIME of each ECCS trip function shown in Table 3.3.3-3 shall be demonstrated to be within the limit at least once per 18 months. Each test shall include at least one channel per trip system such that all channels are tested at least once every N times 38 months where N is the total number of redundant channels in a specific ECCS trip system.

e _- _

Mantte4-testiftg-f 0P-ths pm POI.e-vf*T11tiTiyimj Spvsifi1"Elivu 4.3.3.2 ia ovi iiQuiiC

-ed-stnt4-efter--shutdewet-during-the-44rstwegtsleely -seu dul d rc ftc ! ' M c ut ep

~ - - i we -

ms _ .

CLINTON - UNIT 1 3/4 3-33

  • Attnehment 3

' U-601871 1S-88-042 P a y,e 15 of 4.

TABLE 3.3.3-1 (Continued)

EMERGENCY C0r.E COOLING SYSTEM ACTUAT_ ION lil5TRUMENTAT10N TABLE f10TATIONS (a) A channel may be placed in an inoperable status for up to hours during periods of required surveillance without placing the trip system in the tripped condition provided at least one other OPCRABLE channel in the same trip system is monitoring that parameter.

(b) Also actuates the associated division diesel generator.

(c) Provides signal to close itPCS pump injection valve only.

(d) Provides signal to llPCS pump suction valves only.

b (c) Four reactor vessel water level trip channels are logically combined in a one-out-of-two-twice configuration. For the purposes of the associated ACTION, each one-out-of-two logic is defined as a separate trip system.

(f) Four drywell pressure trip channels are logically combined in a one-out-of-two-twice configuration. For the purposes of the associated ACTION, each one-out-of-two logic is defined as a separate trip system.

(g) One half of these trip channels is associated with Nuclear Systems Protection System (NSPS) Division III; the other half is associated with NSPS Division IV.

  • When the system is required to be OPERABLE per Specification 3.5.2 or 3.5.3.
    • Required when ESF equipment is required to be OPERABLE.
  1. Not required to be OPERABLE when reactor r team dome pressure is < 100 psig.
    1. These Trip Functions are not required for ECCS actuation.

1 The liPCS initiation functions of the Drywell Pressurr - liigh and Manual Initiation are not required to be OPERABLE with indicated reactor vessel water level on the wide range instrument greater than the Level-8 setpoint coincident with the reactor steam dome pressure less than 600 psig.

11 One relay with three inputs in 3 out of 3 logic.

3/4 3-37 Amendment No. 48 CLINTON - UNIT 1

. Attachment 3

, U-601871 L.S 04 2 Page 16 of 42 TABLE 3.3.3-1 (Cpn_tinued)

EMERGENCY CORE COOLING SYSTfH ACTUATION INSTRUMENTATION ACTION  ;

ACTION 30 - With the number of OPERABLE channels less than required by the Minimum OPf.RABLE Channels per Trip Function requirement:

a. With one channel inoperabic, place tfutinoperable channel in the tripped condition withit(f fy3 9erJeelare the associated system inoperabic. qqw@
b. With more than one channel inoperaba, ocuare the associated system inoperabic. .

ACTION 31 - Ocleted.

ACTION 32 - With the number of OPERABLE channels less than required b tha r-Hininum OPERABLE Channels per Trip Function requiremen n 24 declare the associated ADS trip system or ECCS inoperable.- -- -- - -

ACTION 33 - With the number of OPEPJsBLE channels less than the Minimum -

OPERABLE Channels per Trip function requirement, place the _%

inoperabic channel (s) in the tripped condition withiQ.1ht$1 ~'

ACTION 34 - Deleted. ,g ACTION 35 - With the number of OPERABLE channels less than raquTed by the ,

i Minimum OPERABLE the inoperabic Channels per channel to OPERABt.E Trip status Function within hoursrequ$rement, or lrest

^

declare the associated /s05.vs1ve or ECCS inoperabic.

ACTION 36 - With the number of OPERABLE channels less.than required by the Minimum OPERABLE Channels per Trip Function requirement: ,

~

a. for' one trip system._ place that trip system in the tripped ,
condition within@q qqDor declare the HPCS system l inoperable. g4Qy
b. For both trip systenr,meciare the HPCS system inoperable.

~

ACTION 37 - With the number of.0PERABLE channels less than regulred by the Hinimum OPERABLE Channels per Trip Function requirement, place

-- < one inoperable channel in the tripped condition within khout @J M&sa declare-the HPCS system inoperable.

4

ACTION 3B With the number of OPERABLE channels less than the Total Number of Channels, declare the associated emergency diesel generator l

inoperable and take the ACTION required by Specifications 3.8.1.1 or 3.8.1'.2, as appropriate.

ACTION 39 - With the. number of OPERABLE channels one less than the Total Number of Channels, place the inoperable channel in the tripped

-condition within I hour *; operation may then continue until performance of the next required CHANNEL FUNCTIONAL TEST.

ACTION 40 - With the number of OPERABLE channels less than required Ly the Minimum OPERABLE Channels per Trip ' Function requirement, niace _ _ __ _

the inoperable channel in the tripped condition withirGO:#.'24hiwQ =--

t Restore the inoperabic channel to OPERABLE status withiri 7 day ~s

! or declare the associated system inoperable.

  • The provisions of Specification 3.0.4 are not applicable. '

CLINTON - UNIT 1 3/4 3-38

TABLE 4.3.3.1-1 b EFERGENCY CORE COOLING SYSTEM ACTUATION INSTRUMENTATION SURVE1LLANCE REQUIREM

'I E CHANNEL OPERATIONAL FUNCTIONAL CIIANNEL CONDITIONS FOR MIIC11 <

CIWINEL c TEST CALIBRATION SURVEILLANCE REQUIREC

  • CilECK TRIP FUNCTION
  • A. DIV!SION 1 TRIP SYSTEM
1. RHR-A (LPCI HGDE) AND LPCS SYSTEM
a. Reactor vessel Water Level - R 1, 2, 3, 4*,, S*

Low Low Low, Level 1 5 R 1, 2, 3

b. Drywell Pressure - High 5 -H- Q
c. Reactor Vessel Pressure-Low (LPCI and LPCS Injection Valve R(a) 1, 2, 3, 4*, S*

Permissive) S .M-Q

d. LPCI Pump A Start Time Delay 1, 2, 3, 4 * , S
  • Logic Card NA -M-Q Rg ,) 1, 2, 3, 4*, S*

R e.* LPCS Pu:tp Discharge Flow-Low S -H-Q w

LPCI Pump (A) Discharge Flow 1, 2, 3, 4*, S*

1 f.

-Low S -H- R(3) 1, 2, 3, 4 * , S

  • y NA Manual Initiation HA 1 g.

o.

2. AUTCHATIC DEPRESSURIZATION SYSTEM 1 RIP SYSTEM "1"#

ADS IOGIC "A" AND "E"

a. Reactor Vessel Water Level - -H- Q 1, 2, 3 Low Low Low, Level 1 5 ,

R((a)

R a) 1, 2, 3

b. Drywell Pressure-filgh 5 ' -tt- Q R 1, 2, 3
c. ADS Timer NA H-Q
d. Reactor vessel Water Level - *Q RI ") 1, 2, 3 Low, level 3 S {
c. LPCS Pump Olscharge 5 t 4-Q Rf *) 1, 2, 3 Pressure-Ifigh
f. LPCI Pump A Discharge
  • Q RI *) 1, 2, 3 Pressure-High 5 y; 7>

ADS Dry %11 Pressure Bypass x ' &~

g. R 1, 2, 3 Timer NA +4-Q NA 1, 2, 3 $ 3$
h. Manual inhibit ADS Switch NA +t-NA 1, 2, 3 ~EZT
i. Manual Initiation NA oU~3

TABLE 4.3.3.1-1 (Continued)

ENERGENCY CORE COOLING SYSTEM ACTUATION Ih5TRUMEf3TATION SURVEILLANCE REQUI z

$ , OPERATIONAL CA I R TION Su fCE EQ I ED

' c

. TRIP FUNCTION

.-4

" 8. OIVISION II TRIP SYSTEM

1. RHR B AND C (LPCI MODE)
a. Reactor Vessel Water Level - R* 1, 2, 3, %*, 5*

Low Low Low, tevel 1 5 Q. 1, 2, 3 5 -M-Q R

b. Drywell Pressure - High
c. Reactor Vessel Pressure-Low '

(LPCI Injection Valve R(a) 1, 2, 3, 4*, 5*

5 -M-Q Permissive)

LPCI Pump B Start Time Delay ,

1, 2, 3, 4*, 5*

M d.

HA 49-Q R

  1. Logic Card T e. LPCI Pump (B) Dischstge Flow

-tt-Q RI ,) 1, 2, 3, 4*, 5*

5

7. -Low
f. LPCI Pump (c) Discharge Flow 5 -M-Q RI *} 1, 2, 3, 4*, 5*

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

NA

g. rianual Initiation
2. AUTGMATIC DEPRESSURIZATION SYSTEM TRIP SYSTEM "2_"#

ADS toGIC "B" AND "F"

a. Reactor Vessel Vater Level -
  • 1 , 2 ,'3 Low Lcw Low, Level 1 5 ft-Q R(I") 1, 2, 3 5 -N'Q R
b. Drywell Pressure-High R 1, 2, 3 NA M- Q m :- - - >
c. ADS Tleer *, 2
d. Reactor Vessel Water Level - RI *) I, 2, 3 $T
  • g Low, Level 3 5 44- Q 3 3%

LPCI Puep (8 and C) Discharge I

R(,) 1, 2, 3  ;; 3{

e.

Pressure-High 5 -M-Q ,g -2~-

4 ADS Drywell Pressure Dypass { R 1, 2, 3 f.

NA J M-Q 1, 2, 3

- w Timer '

eQ NA "

NA

g. Manual Inhibit ADS Switch NA R NA 1, 2, 3
h. Manual Initiation

~

TABLE 4.3.3.1-1 (Continued)

O EMERGENCY CORE CCOLING SYSTEM ACTUATION INSTRL*. ENTATION SURVEILLANCE REQUIRE

'i o OPERATIONAL

  • Cl!ANNEL
  • FUNCTIONAL CHANNEL CONDITIONS FOR Mf!CH CHANNEL TEST CALIBRATION SURVEILLANCE REGUIRED CllECK l b

.-4 TRIP FUNCTION

  • ' C. DIVISION III TRIP SYSTEM
1. HPCS SYSTEM
a. Reactor Vessel Water Level - R 1, 2, 3, 4*, 5*

Low Low, level 2 5 -M-Q t 1, 2, 3 tb Drywell Pressure-High 5 ,44-Q d R

c. Reactor Vessel Vater Level-High, / R(*) 1, 2, 3, 4*, 5*

Level 8 5 -M-Q g

d. RCIC Storage Tank Level -

, I S 44-Q R(a) 1, 2, 3, 4* , 5*

Low w

2 e. Suppression Pool Water R(a) 1, 2, 3, 4*, 5*

Level - High 5 -M-Q w

f. IIPCS Pu p Discharge Pressure 1, 2, 3, 4*, 5*
  • -liigh 5 -M-G R(,))

g 1, 2, 3, 4*, 5*

' g. HPCS System Flow Rate-Low 5  % R 1, 2, 3, 4*, 5*

NA R NA

h. Manual Initiation
0. LOSS OF POWER NA R 1, 2, 3 , 4 * * . 5 *

1 voltage (Loss of Voltage) H R 1, 2, 3, 4 * * , 5" 4.16 kV Emergency Bus Under- S 2.

voltage (Degraded Voltage) wre>

b

'3SR

~ a 5 iii e., O ~ 2 P

, - - - _. -m

Attachment 3

. _U-601871 1.5-88-042 Page 20 of 42 TABLE t. 3. 3.1-1 (Centinued)

EMERGENCY CORE __C00pHG SYSTEM ACTUATION INSTRUMENTATION SURVE!LLA TABLE NOT ATIONS Not required to be OPERABLE when reactor stearn dome pressure is < 100 psig. ,

  • When the system is required to be OPERABLE per Specification 3.5.2.
    • Required when ESF equipment is required to be OPERABLE.

Calibrate the analog trip module at least once per M-days.

(a) 91 F 4.

3/4 3-47 CLINTON - UNIT 1

Nq

\. .

TABLE 3.3.4.1-1 b ATVS RECIHCULATION PU@ TRIP SYSTEM fNSTRWiENTATIO!I

'i ,

E MINIMUM OPERABLE Of{gyELS i

. PER TRIP SYSTEM c TRIP FUNCTION ,

2  !

  • 1. Reactor. Vessel Water tevel -

" Lcw Low, Level 2 2

2. Reactor Vessel Pressure - High hours for required l One char.nel may be placed in an inoperable status for .sp to (a) surveillance provided the redundant trip system is OPERABLE and monitoring that pararneter.

-tm Y

e 25?R

% 4Es x?se

~R%4 1" E l

f ,'

P 4

TABLE 4.3.4.1-1 b ATWS RECIRrULATIO!i PUMP TRIP ACTUATIOil INSTRUMEllTATION SURVEILLAt1CE REOUIREMENTS 3

E CHAfiHEL FUNCT10tlAl. CilANNEL CllAftNEL i

CllECK TEST CALIBRATI0tt c TRIP FUNCT10tl 5

" 4t- Q , R*

1. Reactor' Vessel Water level - S
  • Low Low, Level 2 ,

-!!- Q R*

2. Reactor Vessel Press'Jte - liigh 5
  • Calibrate trip unit at least once per ays.

5 Y

W 2 G ? ?'

%48"

~ l' ; 9-

" ? 1!

, E O

Attachment 3 U-601871 l 1.S-88-042 Page 23 of 42 INST RUMENT ATION END-OF-CYCtE RECIRCULATION PUMP TRIP SYSTEM INSTRUMENT ATION L1HITING CONDITION FOR OPERATION 3.3.4.2 The end-of-cycle recirculation pump trip (EOC-RPT) system instramen-tation channels shown in Table 3.3.4.2-1 shall be OPERABLE with their trip setpoints set consistent with the values shown in the Trip 5etpoint column of Table 3.3.4.2-2 and with the END-OF-CYCLE RECIRCULATION PUMP TRIP SYSTEM RESPONSE TIME as shcwn in Table 3.3.4.2-3.

APPLICABILITY: OPERATIONAL CONDITION 1, when THERMAL POWER is - > to 40% of RATED THERMAL POWER.

ACTION:

a. With an end-of-cycle recirculation pump trip function instrumentation channel trip setpoint less conservative than the value shown in the Allowable Value column of Table 3.3.4.2-2, declare the channel inoperable until the channel is restored to OPERABLE status with the channel setpoint adjusted consistent with the Trip Setpoint valut.
b. With one of the four channels required for any Trip Function inoperable, operation may contin;e provided the inoperable channel is placed in the tripped condition within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />. The provisions of specification 3.0.4 are not applicable. Nhb@ ~

~

c. With two of the four channels required for any Tr'ip Fuiiction inoperable, place one chani,el in the tripped condition withinfM Jiq0Dprovided no l tripped channel for that Trip Function already exihs. The provisions of Specification 3.0.4 are not applicable.
d. With three of the four channels required for any Trip Function inoperable, reduce THERMAL POWER to less than 40% of RATED THERMAL POWER within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.

SURVEILLANCE RFOUIREMENTS 4.3.4.2.1 Each end-of-cycle recirculation pump trip system instrumentation channel shall be demonstrated OPERABLE by the performance of the CHANNEL FUNCTIONAL TEST and CHANNEL CAllBRATION operations at the frequencies shown in Table 4.3.4.2-1.

4.3.4.2.2 LOGIC SYSTEM FUNCTIONAL TESTS shall be performed at least once per 18 months. Divisional logic and portions of the channel coincident logic shall be manually tested independent of the SELF TEST SYSTEM during each refueling outage uch that all trip functions are tested at least once every four fuel cycle <.

y= - - - _

A '^'9 "*

1. Manual tesung fc+t% pur+cse a sausfying SpecMi"ti r44uhehnt41.-a f4ee-shutdown-duehg-t.he-f4 rst.-cegtHerb c he d u l c d r c f E I N-outege-CLINTON - UNIT 1 3/4 3-52

TABLE 3.3.4.2-1 END-OF-CYCLE RECIRCULATIO!4 PUMP TRIP SYSTEM INcTRUMENTATI0f!

8

  • i c>

MINIMUM OTERABLE

  • NUMBER C CHANNELS FUNCTID'l

((3 TRIP igFs.ARNELS_

O I t< I P

[

TRIP FUNCTION 25 4 2 4 MD)

Turbine Stop Valve - Closure 1.

4 9 gb)

2. Turbine Control Valve-Fast Closure hours for required surveillance (a) A channel may be placed in an inoperable status for up toprovided at least two (b) This function shall be automatically bypassed when turbine first ER. stage pressure is lees than t'

a the value of turbine first stage pressure corresponding to 40% of RATED THERMAL PGV Y

'C 7 5; ? E 7 & Z;;

~ ? ;;; e "222 1" E I

TABLE 4.3.4.2-1 b END-OF-CYCLE RECIRCULATIO!I PUMP TRIP SYSTEM SURVEILLAftCE REQUIREMEllTS Ei E CilAffl:EL

, FUttCTIO!1AL CilAfif4EL TEST CALIBRATION c.

TRIP FUf4CT10tl g R Turbine Stop Valve-Closure -M- Q

" 1.

R

-H- Q

2. Turbine Control Valve-Fast Closure Ma 1

2 5' ? ?

%a?"

~ ? ; ;-

"R" E

O r

Attachment 3

. U-601871

. LS-88-042 Pay,e 26 of 42 f INSTRUMENT ATION 3/4.3.5 REACTOR CORE ISOLATION COOLING SYSTEM ACTUATION INST LIMITING CONDITION FOR OPERATION 3.3.5 The reactor core isolation cooling (RCIC) system actuation instrueenta-tion channels uhown in Table 3.3.5-1 shall be OPERABLE with their f trip set-i points set consistent with the values shown in the Trip Setpoint column o Table 3.3.5-2. 5 SY' OPERATIONAL CONDITIONS 1, 2, and 3 with reactor steam dome na APPLICABILITY:

pressure greater than 150 psig.

ACTION: sYS" a.

With an RCIC system actuation instrumentation channel trip setpoint less conservative than the value shown in the Allowable Value colum 3.3.5-2, declare the channel inoperable until the channel i Setpoint value, b.

With one or more RCIC system actuation instrumentation channels inoperable, take the ACTION required by Table 3.3.5-1.

hann" SURVEILLANCE REQUIREMENTS f Each RCIC system a-tration instrumentat' ion channel shall be demon-4.3.5.1 'B[g TEST and CHANNEL CALIBRATION operations at the fstem f

4.3.5.1-1. d*,'

is 4.3.5.2 LOGIC SYSTEM FUNCTIONAL TESTS shall be performd at least once per 18 months. All RCIC actuation system logic shall be manually tested-h that all trip iLEfu' independent of the SELF TEST SYSTEM l s at least once every four fuel cycle: d O tf4LE els 9;

,e ch3 are tl i

ptW4

.nnew 3e1 t' stem e_

2 i; %

  • MemteHesting-foe-the purpcse-of-sethfyWrpee4f4eet4eald ' . e(ve4H 3-6.- e f

-required-ont44--af tee-s%tdowwJue4eg-the-(4_

cst-cegulef+f-schedu e -c

,.t .,e,- .

I 3/4 3-58 CLINTON - UNIT 1 L

Attachment 3

' U-601871

, LS-88-042

( PaV>e 26 oi 42 l

\

INSTRUMENT AT ION 3/4.3.5 REACTOR CORE ISOLATION COOLING SYSTEM ACTUATION INSTR LIMITING CONDITION FOR OPERATION 3.3.5 The reactor core isolation cooling (RCIC) system actuation instrumenta-l f 4

points set consistent with the values shown in the Trip Setpo Table 3.3.5-2.

OPERATIONAL CONDITIONS 1, 2, and 3 with reactor steam dome APPLICABILITY:

pressure greater than 150 psig.

ACTION:

a.

With an RCIC system actuation instrumentation channel trip setpoint less conservative than the value shown in the Allowable Value column 3.3.5-2, declare the channel inoperable until the channel is Setpoint value, b.

With one or more RCIC system actuation instrumentation channels inoperable, take the ACTION required by Table 3.3.5-1.

SURVEILLANCE REQUIREMENTS 4.3.5.1 Each RCIC system actuation instrumentat' ion channel shall AL be demon-TEST and CHANNEL CALIBRATION operations at the fre 4.3.5.1-1.

4.3.5.2 LOGIC SYSTEM FUNCTIONAL TESTS shall be performed at least once per 18 months. All RCIC actuation system logic shall be manually dtestedeh that all trip fun independent of the SELF TEST SYSTEM l at least once every four fuel cycle

- e_

15  :: nn-ld fue44*9 -

    1. HantiaHesting-for-the-pttrpose-ofmet4sfy4cs-Spee444eet4e --

-otrtegee 3/4 3-58 \

CLINTON - UNIT 1

- - - - - - - _ _ - - - ~ * ' - - - - - - - - - _ - _ _ _ . _ _ _ _ _

_ _ . . . _ .- - . ___ _ - . _ _ . .__.. _ _ __.__. _ -.m-._. -_

Attachment-3 7 U-601871-i LS-88-042 Page 27 of 42 TABLE 3.3.5-1 (Continued) 1 REACTOR CORE ISOLATION COOLING SYSTEM ACTUATION INSTRUMENTATION TABLE NOTATIONS ours for l (a) A channel may be placed in an inoperable status for up to e tripped required surveillance without placing the trip system in condition provided at least one other OPERABLE channel in she same trip system is raonitoring that parameter.

(b) Two trip systems with two channels per trip system.

(c) One trip system with two-out-of-two logic.

(d) One trip system with one-out-of-two logic.

(e) One trip system with one channel.

ACTION ACTION 50 -

With the number of 00ERABLE channels less than-required by the Minimum OPERABLE Channels per Tr.ip System requirement:

a. For 1 trip system, place the inoperable channel (s) and/or -

that trip system in the tripped condition within hou er declare the RCIC system inoperable. 9

b. For both trip systems, declare the RCIC system inoperable.

ACTION.51 - With the number of OPERABLE channels less than required by thel Minimum OPERABLE channels ner_Trittivstem_ requirement, declare the RC M system inoperabi g WiD f4 y u75]

--ACTION 52 - With the number of OPERABLE channels less than required by the Minimum OPERABLE Channels per Trip System requirement,- place at least are Jnoperable channel in the tripped condition--

withi r declare the RCIC system inoperable. [-

ACTION 53 - With the number of OPERABLE channels less +han required by the'.

t, restore Minimum OPERABLE Channels per Trip System requir the-inoperable channel to OPERABLE status withi ours or declare the RCIC system inoperable.

CLINTON - UNIT 1 3/4 3-60

TABLE 4.3.5.1-l' ,

b REACTOR CORE ISOLATI0ft COOLING SYSTEM ACTUATION ItiSTRUMEfiTATI0ti SURVEILLANCE REQU 5

8 CifANNEL CHANNEL FUriCTIONAL CilANNEL e .

CllECK TEST CALIBRATION g FJNCTI_0NAL UNITS

Low Low, level 2

b. Reactor Vessel Water 5 -ff- Q R(a)

Level - liigh, level 8

c. RCIC Storage Tank -M-Q R(3)

S Level - Low

d. Suppression Pool Water Level - S 44-Q R(a) m High s R HA

^ NA w e. Manual Initiation h

days.

(a) Calibrate the analog trip module at least cace pe E a 8 ;'

o ? ;;; e

  • 23P, g~ =

N

TABLE 3.3.6-1 C0flTROL ROD BLOCK IllSTRUMEllTATI0tt b APPLICABLE 5 MIllli!UM OPERATI0tlAL 8 OPERABLE CilAfiliELS f *) C0tfDITI0tl5 ACTI0ft

, PER. TRIP FUt1CTI0ft c TRIP FUt1CTI0t1

= 60

1. ROD PATTERft C0t1 TROL SYSTEM 1, 2

] 2 60

a. Lew Power Setroint 1

. 2

b. RWL ll!gh Power Setpoint
2. APRM 1 61 3 61
a. Flow Biased f;eutron Flux - Upscale 3 1, 2, 5 61
b. Inoperative 3 1

61

c. Downscale 2, 5 3
d. f(eutron Flux - Upscale, Startup
3. SOURCE RAf1GE H0tilTORS 2 61 3 62 R a. Detector'not full in(a) 2** 5 61

^ 2 3

Upscale ID) 5 62 Y b. 2** 61 2

T 3 62

c. Inoperative (b) 2** 5 2 61 3 62
d. Downscale(C) 5 2**
4. If4TERMEDIATE RA! IGE H0!!ITORS 2, 5 61 6 61
a. Detector not full in 6 2. 5 61 Upscale 2, 5
b. 6
c. Inoperative 2, 5 61 Id) 6 d, Downscale
5. SCRAM DISCilARGE VOLUtiE 2

1, 2, 5*

a. Water Level-Ilfgh j{g"
6. REACTOR C00LAftT SYSTEM RECIRCULATIO!! FLOW M (o4 o l' s F.

3 1 eo~g

a. Upscal.e oO~z
7. REACTOR ft00E SWITCll 2

3, 4 63 63 2

o

[

a. Shutdown ttade 5 2
b. Refuct Mode

-wv- - -

m AcIloN G 4 - W:4h%e, number ci ' OPE.RABLE cbnnelt it"GS 4ho rs ^j0 8 "

U required by she M'.n'mun, 0?E RABL6 Channt is per Tr:p 1.s-88-042 Fvno:en reqv:rement, place +5e ;noperate.channet ;n Page 30 of 42

ch the +v pped

~ Cond[MKBEE 3 3 6-1 (Continued)wjmn2S h -

CONTROL ROD BLOCK INSTRUMENTAT]GN TABLE NOTATIONS With more than one control rod withdrawn. Not applicable to control rods removed per Specification 3.9.10.1 or 3.9.1J.2.

    • OPERABLE channels must be associated with SRMs required OPERABLE per Specification 3.9.2-(a) This function shall be automatically bypassed if detector count rate is

> 100 cps or the I!U4 channels are on range 3 cr higher.

(b) This function shall be automatically bypassed when the associated IRM channels are on range B or higher.

, (c) This function shall be automatically bypassed when the IRM channels are on range 3 or higher.

(d) This function shall be automatically bypassed when the IRM channels are on range 1.

(eT A channel may be placed in an inoperable status for up t hours for re-quired surveillance provided at least.one other OPERABLE channel in the same trip ,'anction is monitoring that parameter.

ACTION ACTION 60 -

Declare the RPCS inoperable and take the ACTION required by Specification 3.1.4.2.

ACTION 61 -

With the number of OPERABLE Channels:

a. One less than required by the Minimum OPERABLE Channels per Trip Function requirement, restore the inoperable channel to OPERABLE status within 7 days or place the inoperable channel in the tripped condition within the next hour.
b. Two or more less than requireo by the Minimum OPERABLE Channels per Trip Funct'on requirement, place at least one inoperable channel in the tripped condition within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.

ACTION 62 - With the number of OPERABLE channels less than required by the Minimum OPERABLE Channels per Trip Function requirement, place the inoperable channel in the tripped condition within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.

ACTION 63 - With the number of OPERABLE channels less than required by the Minimum OPERABLE Channels per Trip Function requirement, initiate a rod block.

F CLINTON - UNIT 1 3/4 3-65

' '~

TABLE 4 3.6-1 ,

b CONTROL R00' BLOCK INSTRUMENTATIO'l SURVEILLANCE REQUIREMENTS 5 .t P

z CilAN!!EL OPERAIIONAL. i FUNCTIONAL- CilANt1EL CONDIT10N^ IN WilICil h CllANNEL CllECK TEST CALIBRATION (a) SURVEILLANCE REQUIRED g TRIP FUNCTION

1. R0D PATIERN CONTROL SYSTEM S/U Ib}I*)-

g i i- a. Low Power Setpoint HA D R II) 1, 2 l

[

b. RWL High Power Setpoint HA 5/U(c) d)(e) R II) 1 o I 2.

APRl4

a. Flow Biased Neutron Flux -

Upscale NA S/UID)4t-Q SA 1

b. Inoperative NA S/U :t4-Q _ f1A 1, 2, 5 -
c. Downscale NA ,44-Q SA 1 w d. Neutron Flux - Upscale, Startup- NA 'S/U(b)

$/U ,49-Q SA 2, 5 I

5 3. SOURCE RANGE MONITORS

';' Detector not full in HA NA 2, 5 ,

a. S/U((b)
b. Upscale NA S/U b),W W SA 2, 5

,W 2, 5 _

c. Inoperative NA S/U 11A NA' S/U ,W SA 2, 5 d.'

Downscale

4. INTERMEDIATE RANGE MONITORS I S/U(b) 2, 5 j a. Detector not full in NA S/U(b),W NA 2, 5
b. Upscale NA ,W SA ,

Inoperative S/U ,W NA 2, 5 l

c. NA NA- 5/U ,W - SA 2, 5
d. Downscale
5. SCRAM DISCllARGE VOLUME II)
a. - Water Level-High- S R 1, 2, 5*

i 6.

REACTOR COOLANT SYSTEM RECIRCULATION FLOW

< a. Upscale .NA 5/U(b Q SA 1 2

ce C, e? ?,,

7.

REACTOR MODE SWITCil.

a. Shutdown Mode NA R flA 3, 4 $S8
b. Refuel Mode NA R NA 5 36$I I

., k I C

I g , -.,-.r-9 .~, e --m

Attachment 3'

~ U-601871

. LS-88-042 Page 32 of 42 TABLE 4.3.6-1 (Continued)

CONTROL R00 BLOCK' INSTRUMENTATION SURVEILLANCE REQUIREM TABLE NOTATIONS (a) Neutron detectors may be excluded from CHANNEL CALIBRATION.

(b)

Within 7 days. 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> prior to startup, if not performed within the previous (c) Within one hour prior to control rod movement, unless performed within the previous 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, and as each power range above the RPCS low power setpoint power is entered increase for the first time during any 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> period during or decrease.

(d)

At least once per 31 days while operation continues within a given power range above the RPCS low power setpoint.

. (e) Includes reactor manual control multiplexing system i put.

(f) Calibrate the analog trip module at least once pe ays.

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

l l

l l

l CLlHTON - UNIT 1 3/4 3-69

, .-g, p'

-a Attachment 3 U-601871 s LS-88-042 Page 33 of 42 TABLE 3. 3.7.1-1 (Continued)

RADIATION MONITORING INSTRUMENTATION TABLE NOTATIONS When irradiateo fuel is being handled in the secondary containment.

Alarm only.

With fuel in the new fuel storage vault.

With irradiated fuel in the spent fuel storage pool.

', (a)

A channel may be placed in an inoperable status for up to 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> for re-quired surveillance without placing the trip system in the tripped condi-

, . is monitoring that parameter. tion provided at least one other OPERABLE ACTION ACTION 70 - a.

With one of the required monitors inoperable, place M inoperable channel in the tripped condition with'n[1-ho restore the inoperable channel to OPERABLE status witSi@n 7 days, or, within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> initiate and maintain operation of the control room emerge,ncy filtration system in the high radiation mode of operation.

b.

With both of the required monitors inoperable, initiate and maintain operation of the -control room emergency filtration system in the high radiation mode of operation within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.

ACTION 71 -

With the required monitor inoperable, perform area surveys of the monitored area with portable monitoring instrumentation at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

L.

i l

CLINTON - UNIT 1 3/4 3-72 40 Amendment No.

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Attachment-3 U-601871-

+..

- *: LS-88-042-  :

Page 35 of 42 INSTRUMENTAlION 3/4.3.9 PLANT SYSTEMS ACTUATION INSTRUMENTATION LIMITING CONDITION FOR OPERATION-3.3.9 The plant systems actuation instrumentation channels shown in Table 3.3.9-1 shall be OPERABLE with their trip setpoints set consistent with the-values shown in the Trip Setpoint column of Table 3.3.9-2.

APPLICABILITY: As shown in Table 3.3.9-1.

ACTION:

a.

- With_ a plant system actuation instrumentation channel trip setpoint less conservative than the value shown in the Allowablelalue_ column f..

Tab _le_3.3.9-2, declare tht channel in_operlbleQ K : 5 b T rl 11:

C+oppicabr:

2M_l'X tfifnM CQunfiT the cTannel is Testored M VPERABtE status'wiJhlts tripletioint adjusted consistent with e Trip Setpoint valu g g g g f} W :ih: 9 :5 g :tp:/ ge t = q e ! .

-b. For the containment spray system:

1. - With t'he number of OPERABLE channels less-than required by _the Minimum OPERABLE Channels per containment spray loop requirement for one containment spray. loop, p' lace at least one inoperable channel-in -

the tripped condition within % r declare the associated loop inoperable; l-qWM L 2. With the number of OPERABLE channels less than required by'the ,

L -Minimum OPERABLE Channels per containment spray loop' requirement for- '

L both loops, declare the associated _ loop inoperable, .

c. For_the>feedwater system / main turbine trip system:

, . 1. - With the number 'of OPERABLE channels one less'than required bi the

' Minimum OPERABLE Channels requirement, restore the inoperable channel

' -to OPERABLE status within 7 days or be in at-least STARTUP within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />, t 2. - With the number of OPERABLE channels two less than required by the Minimum OPERABLE Channels requirement, restore at least one _of the L

inoperable channels to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or be in at-least STARTUP within the next.6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.

l

d. For.the suppression pool makeup system (SPMS) with the number of channels.

" one less than the minimum OPERABLE Channels Requirement of Table 3.3.9-1 take the ACTION required by Table 3.3.9-1.'

CLINTON - UNIT 1 3/4 3-97 Amendment No. 40 l

- . .. = . - .. - - . .. . . . - - . ._.-_.-. - - . . . , .. .- . -

i Attachment 3

, LS-88-042 Page 36 of 42 l INSTRUMENTATION PLANT SYSTEMS ACTUATION INSTRUMENTATION SURVEILLANCE REQUIREMENTS 4.3.9.1 Each plant system actuation 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 4.3.9.1-1.

4.3.9.2 LOGIC SYSTEM FUNCTIONAL TESTS shall be performed at least once per 18 months. Each trip system or division of the plant system actuation logic associated with the Nuclear System Protecti~on System shall be manually tested independent of the SELF TEST SYSTEM during separate refueling cutages such that all di defor> :nd all trip functions are tested at least once every four fuel cycles "*-

l i

l l

l i-

,p EHanttei--tes t i ng -f o r t hc --p u rp ;; ; o f :o t i ; fy i ng @ee444et4c n ' . 2. 9, 2 i t ne t-eequiced-enthf4ee-shistdowr-due4eg-tt "r t-r+9eler!y scheduk4-refue14^7 StG9Er ..

l CLINTON - UNIT 1- 3/4 3-98 Amendment No. 40

I

( -

TABLE 3.3.9-1 9 PLANT SYSTEMS ACTUAT10ti Ir4STRUME!iTATION g

l $

= rilNIMUM OPERABLE l ' CilANNELS PER APPLIr!3tE CONTAINMErlT OPERATIUNAL E SPRAY LOOP CONDITIONS

  • TRIP FUNCTION
a. 1, 2, 3
b. Containment Pressure-High 2*
c. Reacter Vessel Water '.evel-tow low Low, level 1 2* 1, 2, 3
d. Timers 1, 2, 3 (1) Loop A, Loop B (10 minutes) 1 1, 2, 3 (2) Loop B only (90 seconds) 1 1 1. 2, 3 y e. Manual Initiation a

MINIMUM OPERABLE y

2. FEE 0 WATER 5YSTEM/ MAIN TURBINE TRIP SYSTEM Reactor Vessel Water Level-High, level 8 3* .1 a.

MINIMUM OPERABLE CHArmELS PER TRIP SYSTEM ACTION

3. SUPPRESSION POOL MAKEUP SYSTEM 2* 1, 2, 3 50
a. Drywell Pressure-High 1, 2, 3 50 Reactor Vessel Water Level-Low Low Low, level 1 2*
b. 1, 2, 3 51 Suppression Pool Water Level-tow low 2*
c. 1 1, 2, 3 51
o. Suppression Pool Makeup Timer 1,2,3 51 2

y e. SPMS Manual Initiation 1 1,2,3 51 ,c, g f. SPMS Mode Switch Permissive

$???

k s

':Sa g

  • A channel may be placed in an inoperable status for up t lours for required surveillance without O6$f 2

,o placing the trip system in the tripped condition previded at least one other OPERABLE channel in oC2 g the same trip system is monitoring that parameter. E

  • Attachment 3

,_ U-601871

. LS-88-042 Page 38 of 42 TABLE 3.3.9-1 (Continued) ,

QANT SYSTEMS ACTUATION INSTRUMENTATION ACTION ACTION 50 - With the number of OPERABLE channels less than required by the Mininum OPERABLE Channels per Trip System requirement:

a. For1tripsys+.em,p!acetheinoperablechannel(sland/or s

that or trip system declare the SPMS ininoperable the tripped andcondition within[ge-h{@Q take the action or -- --

l Specification 3.6.3.4.

. b. For both trip systems, declare the SPM5 inoperable and take the action of Specification 3.6.3.4.

,_ ACTION bl - With the number of OPERABLE cnannels less than required by the Minimum OPERABLE channels par Trip System requirement,

-* declare the SPMS system inoperat',e and take the action of Specification 3.6.3.4. l

- rc5+cfc 4hc 'inegrabte channel (C b OPERABW Shh6 w'i4W G 29 boo f5 o e

~~~w A' 4

CLINTON - UNIT 1 3/4 3-100 Amendment No. 40

~

e'. '

n TABLE 4.3.9.1-1 C

$ PLANT SYSTEMS ACTUATION INSTRUMENTATION SURVEILLANCE REQUIREMEt E

E CilANNEL OPERATIONAL CilANNEL FUNCTI0t1AL CHAtNEL Z TRIP FUNCTION CHECK TEST- CONDITIONS IN WlilCH w CALIDRATION SURVEILLANCE REQUIRED

1. CONTAltlMENi SPRAY SYSTEM
a. Drywell Pressure-High 5
b. -M- Q R 1, 2, 3 Containment Pressure-High 5 R' I
c. Reactor Vessel Water Level-Low -H- Q 1, 2, 3 Low Low, level 1 l
d. Timers 5 -!t Q R(a) 1, 2, 3
e. Manual Initiation NA 4bQ R 1, 2, 3 ilA flA 1,2,3

$ 2. FEEDWATER SYSTEM / MAIN TURBINE TRIP SYSTEM T a. Reactor Vessel Water Level-High,

[o Level 8 S R 1

3. SUPPRESSION POOL MAKEUP
a. Drywell Pressure-High 5 -H- Q R(a) 1, 2, 3
b. Reactor Vessel Water Level -

Low Low Low, level 1 5 -M. Q , R ld) 1, 2, 3

c. Suppression Pool Water Level-Low Low S 46- Q j R(b) 1. 2. 3

[ d. Suppression Pool Makeup Timer NA -M- Q Q 1, 2, 3

~

e. SPMS Manual Initiation lA R 2 NA 1,2,3 '
f. SPMS Mode Switch Permissive

'J

e. G.en ?R

[ NA R NA 1,2,3 [yhh 1o *R==4 (a)Calibra.te the analog trip module at least once eve 91 -M- da oo

=

~

(b) Calibrate the analoi compar4 tor nit at least once eve ays.

3 m

a, ,

o

0 Attachment 3 U-601871 LS-88-04?

f.

I o.

Page 40 of 42 REACTOR COOLANT 5'isTEM 3/4.4.2 SAFETY VALVES SAFETY / RELIEF VALVES LIMITING CONDITION FOR OPERATION 3.4.2.1 The safety valve function of at least six of the fo' lowing valves and the relief valve function of at least five additional valves, other than those 4

satisfying the safety valve function requirement, shall be OPERABLE with the specified lif t settings; ano the acoustic monitor for each OPERABLE valve shall be OPERABLE.*

Nueber of Valves Function setnoint** (psic) 7 Tafety ITB3 1 11.6 psi ~

5 Safety 1380 1 11.8 psi 4 Safety 1190 1 11.9 psi 1 Relief 1103 1 15.0 psi 8 Relief 1113 15.0 psi 7 Relief 1123 1 15.0 psi app 1,ICABILITY: OPERATIONAL CONDITIONS 1, 2, and 3.

ACTION:

a. With the safety and/or relief valve function of one or more of the above required safety / relief valves inoperable, be in at least HOT SHUT 00VN 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 rext 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />,
b. With one or more safety / relief valves stuck open, provided that suppres-sion pool average water ternperature is less than 110'F, close the stuck open safety / relief valve (s); if suppression pool average water tempera-ture is 110 F or greater, place the reactor mode switch in the Shutdown position,
c. With one or more safety / relief valve acoustic monitor (s) inoperable, restore the inoperable monitor (s) to OPERABLE status within 7 days or be in at least HOT bluTDOWN 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 SHUTOOWN within the "ollowing 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
d. With either relief valve function pressure actuation trip system "A" or "B" inoperable, restore the inoperable trip system to OPERABLE status within 7 days; otherwise, 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 COLO 5HUTDOWN within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
  • One relief valve pressure actuation channel and/or one stic conitor channel may be placed in an incperable status for up to ours for the purpose of performing surveillance testing in accordance ith Specifica-tions 4.4.2.1.1 and 4.4.2.1.2.
    • The lift setting pressure '. hall correspond to ambient conditions of the valves at nominal operating temperatures and pressures.

CLIHTON - UNIT 1 3/4 4-9

h_

  • Attachment 3

> 4.4.2,1.1 The acoustic monitor for each safety / relief valve shall be demonstrated OPERABLE by performance of a:

a. CHANNEL FUNCTIONAL TEST at least once per 31 days, and a
b. CHANNEL CALIBRATION at least once par 18 months.*

4.4.2.1.2 The relief valve function pressure actuation instrumentation shall be demonstrated OPERABLE by performance of a:

a. CHANNEL F CTIONAL TEST, including calibration of the trip unit, at least once pe 1. ays.
b. CHANNEL A IBRATION and LOGIC SYSTEM FUNCTIONA: TEST at least once per 18 months. Each of the two trip systems or div4' ons of the ralief valve function actuation logic associated wit' t' .uclear System Protection System shall be manually tested indepe ... of the SELF TEST SYSTEM during separate refueling outages such that both divis e and all channel trips are tested at least once every four fuel cycles ~ g
  • The provisions of Specification 4.0.4 are not applicable provided the surveil-lance is performed within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> after reactor steam pressure is adequate mto perform j e test _ _

^^Mance t-te iting-f or-t _ __urpose-of--sat 4sfyang-4pacL*4 cat 4on ' A . 2, L 2. b. E a ^ +c requiredwnt44--af-tec-shutdown-duMog-the-f4rst-regulaMy-scheoWed :f =l'ng-eutages CLINTON - UNIT 1 3/4 4-10

, At t achment 3 U-601871

+ LS-88-042 REAC10R COOLANT SYSTEM Pap 42 of 42 SAFETY / RELIEF VALVES LOW-LOW SET FUNCTION LIMITING CONDITION FOR OPERATION 3.4.2.2 The low-low set function of the following reactor coolant system safety / relief valves shall be OPERABLE with the following settings *:

Low-Low set Function Setpoint* (psig) 2 15 psi Valve No. Open Close F0510 1033 926 F051C 1073 936 F047F 1113 946 F051B 1113 946

. F051G 1113 946 APPLICABILITY: OPERATIONAL CONDITIONS 1, 2, and 3.

ACTION:

a. Witt, the low-low set function of one of the above required reactor coolant system safety / relief valves inoperable, restore the inoperable low-low set function to OPERABLE status within 14 days 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 SHUTOOWN within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
b. With the low-low set function of more than one of the above required reactor coolant system safety / relief valves inoperable, be in at least HOT SHUTOOWN 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 />.
c. With either low-low set function pressure actuation trip system "A" or "B" inoperable, restore the inoperable trip system to OPERABLE status within 7 days; otherwise, be in at least HOT SHUTOOWN within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLD SHUT 00VN within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

SURVElLLANCE REQUIREMENTS 4.4.2.2 The low-low set function pressure actuation instrumentation shall be demonstrated OPERABLE by performance of a:

a. CHANNEL FU' CTIONAL TEST, including calibration of the trip unit, at least once per -ri days. I 91-
b. CHANNEL CALIBRATION and LOGIC SYSTEM FUNCTIONAL TEST at least once per 18 months. E~ach of the two trip systems or divisions of the low-low set function actuation logic associated with the Nuclear System Protection System shall be manually tested independent of the SELF TEST SYSTEM during separate refueling cutages such that both divisi ns and all channel trips  ;

are tested at least once every four fuel cycles I

  • 0ne channel may be placed in an inoperable status for up to hours for the pur-pose of performing surveillance testing in accorcance with Specification 4.4.2.2.
    • The lift setting pressure shall correrpond to ambient conditions of the valves a t_ noni n,,jtL;grjiQnq tempe ra t u re s a nd _p r e s s u re s . __ - #

" i 5 'F *e 4f4anua4--t.es14ng--foAhe-T>urpbse-44--sMi ty V -

qu ired-u n t44-e f ter-s huttown-dttrbg--tM4tM- regu4er4 y s ch t d u l : d -ac f a l ' atdwl-3e CLINTON - UNIT 1 3/4 4-11 Amendment No. 5

--_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _

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