ML20128M701

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Proposed TS 3/4.3.3 Re ECCS Actuation Instrumentation & TS 3/4.3.5 Re RCIC Sys Actuation Instrumentation
ML20128M701
Person / Time
Site: Clinton Constellation icon.png
Issue date: 02/17/1993
From:
ILLINOIS POWER CO.
To:
Shared Package
ML20128M691 List:
References
NUDOCS 9302220251
Download: ML20128M701 (16)
v • d • e


Text

_ .- . . _ _ . . _ _ - - . - _ _ _ - __ - __ - -_ _ _. .__ -_

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LS-88-042 Page 14 of 42 INSTRUMENTATION 3/4.3l3 EMERGENCY CORE COOLING SYSTEM ACTUATION INSTRUMENTATION L1HITING CONDITION FOR OPERATION

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 setpointa set consistent with the values shown in the Trip Setpoint column of Table 3.3.3-2 and with EMERGENCY CORE COOLING SYSTEM RESPONSE T!HE as shown i 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 untti 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 systems 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 the 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 press. u re to 1100 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 4.3.3.1 Each ECCS actuation instrumentation channel shall be demonstrated OPERABLE by the performance of the CHANNEL CHECX, CHANNEL FUNCTIONAL TEST and CHANNEL CALIBRATION operations for the OPERATIONAL CONDITIONS and at the frequencies shown in Table 4.3.3.1-1.

LOGIC SYSTEM FUNCTIONAL TESTS shall be perforned at least once per 18 4.3.3.2 The actuation system logic associated with each of the ECCS divisions months.

h b er o shall be manually tested independent of the SELF TEST SYSTEM during alternatei refueling outages such that all d 00 least once every four fuel cycles l

MW)

N 4.3.3.3 The CCCS RESPONSE-TIME of each ECCS trip function shown in Table Each3.3J-3 shall be demonstrated to be within the limit at least once per 18 months.

W test shall include at least one' channel per trip system such that all channels

~Q Oc are telted at least once every N times 18 months where H is the total number of redundant channels in a specific ECCS trip system.

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  • . D.eul 1sadi.j Is. tk yw.ywas wI ssi$a fy $ ig Syw I'aw iswo 4.3.3.2
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1, TABLE 3.3.3-1  ;

i j n '

C- EMERGENCY CORE COOLING SYSTEM ACTUATION INSTRUMENTATION I

j 5 j 4 E MINIMUM OPERABLE APPLICABLE  ;

i CHANNELS PER TRIP OPERATIONAL ACTION j E FUNCTION CONDITIONS _

-p TRIP FUNCTION r t

A. DIVISION I TRIP SYSTEM '

i

1. RHR-A (LPCI' MODE) & LPCS SYSTEM i
a. Reactor Vessel Water Level - Low Low Low, b)(a) C 1, 2, 3, 4* , 5* 30 i

. Level 1 2(I )

  • 5*) 1, 2, 3 30 f l
b. Drywell Pres m re - High 2*

4 I C) 1, 2, 3 32 i

! c. Reactor Vessel Pressure-Low 4*, 5* 33 [

(LPCI and LPCS In,lection Valve Permissive) 5* i j.

d. LPCIPump(A)StartTimeDelayfogicCard IdN 1, 2, 3, 1, 2, 3, 4*,

4*, 5*

32 40 t

R e. LPCS Pump Discharge Flow - Low LPCI Pump (A) Discharge Flow - Low #,

1f* 1, 2, 3, 4", 5* 40

'

  • f. - If 1 1, 2, 3, 4*, 5* 35 y g. Manual Initiation
2. AUTOMATIC DEPRESSURIZATION SYSTEM TRIP SYSTEM "1"# .

ADS LOGIC "A" AND "E" i

{

a. -Reactor Vessel Water level - Low Low Lcw, g 30 Level 1 2(, 4) 1, 2, 3 1,2,3 30 I

?

j- b. Drywell Pressure.- High 2 8,) g 1, 2, 3 32

c. ADS Timer I l
d. . Reactor Vessel Water level - Low, 1, 2, 3 h i 1

i Level 3 (Permissive)

LPCS Pump Discharge Pressure-High 1[D ,j ,

j j- e. 2(p ,")/ 1, 2, 3 32

.(Permissive)

?

f. . LPCI Pump (A) Discharge Pressure-High I 1,2,3 3 .l l

g.

(Permissive)

ADS Drywell Pressure Bypass Timer 226')b 1, 2, 3 3 2. - -

1~ 1, 2, 3

h. Manual Inhibit ADS Switch 2 1, 2, 3 35
j. i. Manual Initiation  :
.o O CD i

PJ 2*

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- bD

TABLE 3.3.3-1 (Continued)

S EMERGENCY CORE COOLING SYSTEM ACTUATION INSTRU"ENTATION 5

E MINIMUM OPERABLE APPLICABLE

, CHANNELS PER TRIP OPERATIONAL CONDITIONS ACTION c- FUNCTION E5 TRIP FUNCTION

" B. DIVISION II TRIP SYSTEM

1. RHR B & C (LPCI HODE)
a. Reactor Vessel Water Level - Low Low Lcw, g)g g 1, 2, 3, 4*, 5* 30 Level 1 2(b) e) , 1, 2, 3 30
b. Drywell Pressure - High 2(,

4 1,2,3 32

c. Reactor Vessel Pressure-Low 4*, 5* 33 (LPCI Injection Valve Permissive) 1 1, 2, 3, 4*, 5* 32
d. LPCI Pu:m.(B) Start Time Delay Logj C6) e 1, 2, 3, 4*, 5* 40 l
e. LPCI Pump (B) Discharge Flow - Lcw,p Card 1 "I 1, 2, 3, 4*, 5* 40 w LPCI Pump'(C) Discharge Flow - Low ,

~

1,2,3,4*,5* 35 2 f.

g. Manual Initiation 1

u M 2. AUTOMATIC DEPRESSURIZATION SYSTEM TRIP SYSTEM "2"#

AND "F" ADS LOGIC "B"

a. Reactor Vessel Water Level - Low Lew Lcw, g 1,2,3 30 .

Level 1 2 ,a ( 1, 2, 3 30 2

b. Drywell Pressure - High '9 1,2,3 32
c. ADS Timer
d. Reactor Vessel Vater Level - Low, level 3 I M 1,2,3 30 ::  !

i

' (Per=1ssive)

e. LPCI Pump (B and C) Discharge Pressure - 1, 2, 3 37 High (Permissive) 2/p) 2te DIE))

1, 2, 3 32.

  • l
f. ADS Drywell Pressure Bypass Timer 1 1,2,3 n
g. Manual Inhibit A05 Switch 2 1,2,3 35 ,
h. Manual Initiation  :

n, o N

%eT i w A E-E

~.

n TABLE 3.3.3-1 (Continued)

C.

5 EMERGENCY CORE COOLING SYSTEM ACTUATION INSTRUMENTATION E

' APPLICABLE MINIMUM OPERABLE OPERATIONAL k CHANNELS PER TRIP FUNCTION CONDITIONS ACTION TRIP FUNCTION

.4

>4-C. DIVISION III TRIP SYSTEM

1. HPCS SYSTEM Reactor Vessel Water Level-Lew, Low, level 2 4 9 8) 1, 2, 3, 4*, 5* 36

- a. 7 9 (6)

b. Dowell Pressure - High t 4 1, 2, 3 3
c. Reactor Vesse12 Water Level-High, level 8 fC){9)

)C 1, 2, 3, 4* ' 5* ~ #s

.J d.

e.

RCIC Storage Tank ~ Level-Low Suppression. Pool Water Level-Highgg 2]C 2

2 3Cf3 1, 2, 3, 4 * , 5

  • 1, 2, 3, 4*, 5* 37
f. HPCS Pump Discharge, Pressy"t;e-High 1 1, 2, 3, 4*, 5*

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

  • I
g. HPCS; System Flow Rate-Low w 1 1, 2, 3, 4*, S*

J h. Manual Initiation t Y MINIMUM APPLICABLE M TOTAL NO. CHANNELS OPERABLE OPERATIONAL OF CHANNELS TO TRIP CHANNELS CONDITIONS ACTION D. LOSS OF POWER

1. 4.16 kV Emergency Bus,.Undervoltage (Loss of Voltage) a.- Divisions I & II 2/ Division 2/ Division 2/ Division 1, 2, 3, 4**, 5** 38 2 4 1, 2, 3, 4**, 5** 28
b. ' Division III 4

_ 2. 4.16 kV Emergency Bus Undervoltage

g. (Degraded Voltage)

Divisions I & II 2/Divistor, 2/ Division 2/ Division 1, 2, 3, 4**, 5** 39 g a. 1, 2, 3, 4**, 5** 39 3 3

g. b. Division III ?? 3 e

'3,

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Attachment 3 to U-602078 Page 5 of 16 4

i I Attachment 3 l U 601871 LS 68 042

] Page 15 of 42 l TADLE 3.3.3-1 (Continued) a

! EMERGENCY CORE COOLING SYSTEH ACTUATION INSTRUMENTATION

} TABLE NOTATIONS l' (a) A channel may be placed in an inoperable status for up to hours du-Ing periods of required surveillance without placing the trip system in the  ;

tripped condition provided at least one other OPERABLE channel in the '

same trip systers is monitoring that parameter.  !

(b) Also actuates the associated division diesel generator, l

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

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

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

I a When the system is required to be OPERABLE per Specification 3.5.2 or 3.5.3.

l Required when ESF equipment is required to be OPERABLE.

4

# Not required to be OPERABLE'when reactor steam dome pressure is 1100 4 psig, i
    1. These Trip functions are not required for ECCS actuation.

I t The HPCS initiation functions of the Drywell Pressure - High and Manual Initiation are not required to be OFERABLE with-indicated reactor vessel

~

water level on the wide ranDe instrument greater than the level-8 setpoint

, coincident with the reactor steam dome pressure less than 600 psig.

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

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@ 'the.se. channels ofe. fequ'iree \n order 40 ma W n auiernaMc. irip cambil 33 c6 Iclen+;9:ect in +he associcded AC.T ON stdements, _ f

- x  : _ 2 CLINTON --IINTT 1 3/4 3-37 Amendment No. 48

I ,

Attachment 3 to U-602078 l 7 , Page 6 of 16 '

Re
dace Wh Teed L - -

Attachment 3

! U-601871 1

1.S88-042 Page 16 of 42 TABLE 3.3.3-1 (Continued)

EMERGENCY CORE COOLING $YSTEM ACTUATION INSTRUMENfATION ACTION _

i

,,, W .

,r y V__

AC : R3 ' - With the number of OPERABLE channels less than required by the

' Hinimum OPERABLE Channels per Trip Function requirement:

q I a. With one channel inoperable, place thrinoperable channel j

in the tripped condition withit -f 6f.9er_ declare the associated system inoperable. qwoof

b. With more than one channel inoperabse, ceciare the associated j 4# h syst1m inolerablez j e __ e -

q__ _

Orleted ON 11 (C](

j NC110N 12 With the number of OPERABLE channels less than required by t a --

Hinimum- OPERABLE Channels per Trip function requiremen m 24 h

_ declare the associated ADS trip system or ECCS inoper i

-- - J l . _ _ ~

l IciFON l i- With ttFe number of OPIRABLE channels less than the Hiiiimum~

OPERABLE Channels per Trip function ~ requirement, place the h

inoperable channel (s) in the tripped condition withiQ(2Nhs ~

AC1.ON 3 <- Deleted. ,

g ACT OH 31- With the number of OPERABLE channels less tlutn reqUITjd by the Hinimum OPERABLE Channels per Trip Function requ irement, restore j

the inoperable channel to OPERABLE status within$ hours or l sa'= % declare the associated ALS valve or ECCS inoperable:

l ~

I CTl N36 With'the number'of OPTRABLE channels less.Gan required by the Hinimum OPERABLE Channels per Trip function requirement:

(l For one trip system, place tidt trip' system'in the' tripped

~

l a.

condition withi m c. = or declare the HPCS system ~ l l

! inoperable. 'h *c_the lipCS system inoperable. l i b. For both trip syste2. , _

At '10N - With the number of.0PERABLE cTannels less tEan requ. ired by the ,

Hinimum OPERABLE Channels per Trip Function requirement. . place f m tJeast one inoperable channel in the tripped condition within a

2 j hpf_Q-1-hour 9er declare the HPCS system inoperablex r ACI QW3tf- 7itif the number ciOPERABLE channels less than the Total Number of Channels, declare the associated emergency diesel generator l inoperable and take the ACTION required by Specifications 3.0.1.1 l or 3.8.1.2, as appropriate.

i

, ACT! 39 - With the number of OPERABLE channels one less than the Total

' Humber of Channels, 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 /> *; operation may then continue unt.il f rformance of the rtext renoired CHANNEL FUNCTIONAL._ TEST. _ __

l ACTION - Viih tTe number of OPE'RABLE cIiannels less than' required l'y the Hicimum OPERABLE Channels per Trip Tunction requirement ol_ ace _ _ -_ i t'ae inoperable channel in the tripped condition withi ~ ayYc teuei2%g i uestore the inoperable channel to OPERABLE status with or declare the associated system inoperable. _

I "The provisions of Specification 3.0.4 are not applicable, e ,ma.. . . ... e v , 3/4 3 3g

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r -mi t+e--*-

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Attachment 3 to U 602078 Page 7 of 16 1pa rt for par.e 3/4 3 38 ACTION 30 With the nuraber of OPEPABLE channels less than required by the Minianum OPERABLE Channels per Trip Function requirement, verify within one hour that a sufficient number of channels reinain OPEPABLE or are in the tripped condition to inaintain autoinatic actuation capability of either Division I or Division 11 ECCS and either ADS Trip System 1 or Trip System 2, and place the inoperabic channel (s) in the tripped condition within 24 houra*. Otherwise, declare the associated system (s) inoperable. l ACTION 32 - With the number of OPERABLE channels less than required by the Minimurn OPERABLE Channels per Trip Function requirement, verify within one hour that a sufficient number of channels remain OPERABLE or are in the tripped condition to maintain automatic actuation capability of either Division 1 or Division II ECCS and either ADS Trip System 1 or Trip System 2, and restore the inoperable channel (s) to OPERABLE status within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. Otherwise, declare the associated ADS trip l system (s) or ECCS inoperable.

ACTION 36 With the nuinber of OPERABLE channels less than required by the Minimurn OPERABLE Channels per Trip Function requirement, verify within one hour that a sufficient number of channels remain OPERABLE or are in the tripped condition to maintain automatic HPCS actuation capability, and place the inoperable channel (s) in the tripped condition within 24 l hours *. Otherwise, declare the HPCS system inoperable.

ACTION With the number of OPERABLE channels less than required by the Minimtun OPERABLE Channels per Trip Function requirement, verify within one-hour that the HPCS pump suction is either aligned or is capable of automatically realigning to the suppression pool, and place at least one inoperable channel in the tripped condition withir 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> *, otherwise.

declare the llPCS system inoperable, l ACTION 40 - With the number of OPERABLE channels less than required by the Minimum OPERABLE Channels per Trip Function requirement, verify within one hour that a sufficient number of channels remain OPERABLE or are in the tripped condition to maintain automatic actuation capability of either D1_ vision I or Division II ECCS, and restore the inoperable channel (s) to OPERABLE status within 7 days. Otherwise, declare the associated system (s) inoperable.

ACTION 41 - With the number of On..ABLE channels less than required by the Minimum OPERABLE Channels per Trip Function requirement, restore the inoperable channel (s) to OPERABLE status within 7 days. Otherwise, declare the'HPCS system inoperable.

U b Attachment 3

%I6 @ Trou;ded i,,[8 0'8 6

^

( $h W On ,

Attachmes 3 U 601871

!.?-A8 042 Page 26 of 42 INSTRUMENTATION 3/4.3.5 REACTOR CORE }$0LAT10N C00 LING SYSTEN ACTUATION IN$TRUMENTATION LlHITING CONDITION FOR OPERATION 3.3.5 The reactor core isolation cooling (RCIC) system actuation instrumenta*

tion channels shown in Table 3.3.51 Shall be OPERABLE with their trip set

  • points set consistent with the values shown in the Trip Setpoint column of Table 3.3.5 2.

APPLICABILITY: OPERATIONAL CONDITIONS 1, 2, and 3 with reactor steam dome pressure greater than 150 psig.

ACTION:

a. With an RCIC system actuation instrumuntation channel trip setpoint less

~

conservative than the value shown in the Allowable Value colu.an of Table 3.3.5-2, declare the channel inoperable until the channel is restered to CPERABLE status with its trip.setpoint adjusted consistent with the Trip 5etpoint value.

b. With one or more RCIC system actuation instrumentation channels inoperable, take the ACTION required by Table S.3.5-1.

SURVEILLANCE REQUIREMENTS 4.3.5.1- Each RCIC system actuation instrumentation channel shall be demon

  • strated CPERABLE by the performance of the CHANNEL CHECK, CHANNEL TUNCTIONAL TEST and CHANNEL CALIBRATION operations at the frequencies shown in Tele 4.3.5.1-1.

4.3.5.2 LOGIC SYSTEM TUNCTIONAL TESTS shall be performed at least once per 18 months. All RCIC actuation system logic shall be manually tested independent of the SELF TEST SY$ TEM h that all trip functions are tested at least once every four fuel cycles l l

r i

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5._}I!,*f.S. 55.555!N. 555., b- --b b S N g-

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I" T-e"94e.--:[.-1.5_?_ii v - --

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C1.1NTON - UNIT 1 3/4 3-58

--___a_,,.. . ~. . - _.-.u-. _- - , . _ . _ _

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

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TABLE 3.3.5-1 o

3 t.

REACTOR CORE ISOLATION COOLING SYSTEM ACTUATION INSTRLHENTATION%

g  ?

! 3 k g 56, T J a MINIMUM gy C f' D ~~

l l

! OPERABLE CHANNELS  !

j c

5 PER TRIP SYSTEM ACTION 1

% i j

FUNCTIONAL UNITS Reactor Vessel Water Level - Low Low, level 2 2(b)(a) 50 I,

3 f '

a. I M  :

l 2(c) 51 '

f Reactor Vessel Water Level - High, Level 8 I

b. g )

2(d)(a) 52

c. RCIC Storage Tank Water Level - Low l 2(d)(a) 32
d. Suppression Pool Water Level - High I I ') 53 ,
e. . Manual Initiation t 1

. ~

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q' '

3 4 e+ >

E*"

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

Attechment 3 to U-602078 Page 10 of If i

i Attachment 3 5 U-601871 I LS-88 042 Page 27 of 42 TABLE 3.3.5-1 (Continued)

I REACTOR CORE 150LAT10N COOLING SYSTEM ACTUATION INSTRUMENTAT

TABLE NOTATIONS

. hours for l (a) A char,ael may be placed in an inoperable status for up to required surveillance without placing the trip system in t e tripped

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

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

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

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

4 (e) One trip system with one channel.

ACTION v v v ~ ~ , c ~

j With the number of OPERABLE channels less than required by the ACTION 50 - Hinimum OPERABLE Channels per Tr.ip System requirement:

l I

P

a. For 1 trip system place the inoperable channel (s) and/o ' hours 4

that trip system In the tripped condition within ~M 7 l

or declare the RCIC system inoperable. (

b.

For both trip systems, declare the RCIC system inopera

- With the number of OPERABLE channels less than required by the ACTION 5 Hinimum OPERABLE channels pur T inJvstem_ requirement, declare the RCIC system inoperab1NWM 2,3)uM _ _

, ~

52 - With the number of OPERABLE channeTs less than required by the l ACTI Minimum OPERABLE Channels per Trip System requirement, place at leas noperable channel in the tripped condition r declare the RCIC system inoperable. l i

withi j

3- With The num7er of CPERABIE channels.less than required by the AC 10t Minimum OPERABLE Channels per Trip System requirer nt, restore the inoperable channel to OPERABLE status withi 2.

e ours or declare the RCIC system inoperable.

CCv y ,

f l

le? et l WA Irv5ed - - _

l. 3/4 3-60 CLINTON - UNIT 1 l

.' . Attachasnt 3 to U 602078 Page 11 of 16 Insert for nane 3/4 3-60 i

l, ACTION 50 With the number of OPERABLE channels less than required by the Minimum OPERABLE Channels per Trip System requirement, verify within one hour that a sufficient number of low reactor vessel water level channels remain OPERABLE or are in the tripped condition to maintain rutomatic RCIC system actuation capability, and place the inoperable channel (s) in the tripped condition within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. Otherwise, declare the RCIC systern inoperable.

ACTION 52 - With the number of OPERABLE channels less than required by i the Minirnum OPERABLE Channels por Trip System requirement, verify within one hour that the RCIC pump suction is aligned or will automatically realign to the suppression pool, and place at least one inoperable channel in the tripped condition within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. Otherwise, declare the RCIC system inoperable, i

3 i

f 1

J d

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

~ _ . . _ . _

I TABLE 3.3.6-1 - @

.n CONTROL ROD BLOCK INSTRUMENTATION D

{ l  :) ]

N HINIMI APPLICABLE

, OPERATIONAL 4 O M OPERABLE CllAFCiEL3(*)CONDITIONS PER TRIP FUNCTION

,i g TRIP FUNCTIOf4 ACTION l

1. ROD PATTERN C0!! TROL SYSTEM
a. Low Power Setpoint 2 1, 2 60

{ T' J, h

{

b. RWL Illgh Power Setpoint 2 1 60 0 C.

4

2. APRM 2
a. Flow Diased I;cutron Flux - Upscale b.

c.

Inoperative Downscale 3

3 3

1 1,2,5 1

61 61 61 O ft 3 K [l}

d. Neutron Flux - Upscale, Startup 3 2, 5 61 { ,
3. SOURCE RANGE HONITORS t'
a. Detector not full in(a) 3 2 61 1 2** 5 62
  1. 1;* b. Upscale (b) 3 2 61 S: 2** 5 62
c. Inoperative (b) 3 2 61 2** 5 62
d. Downscale fC) 3 2 61 2** 5 62
4. INTERHEDIATE RANGE MONITORS
a. Detector not full in 6 2, 5 61
b. Upscale 6 2, 5 61
c. Inoperative 6 2, 5 61
d. Downscale(d) 6 2, 5 61
5. SCRAM DIStilARGE VOLUME 6.
a. Water Level-liigh REACTOR COOLANT SYSTEM RECIRCULATIO!I FLOV 2 1, 2, 5*

[

  • 7 a ;;

amo.

a. Upscal.e 3 1 e(o4 y?g4
7. REACTOR MODE SWITCII ohUh"
a. ' Shutdown Mode 2 3, 4 63
b. Refuel Mode 2 5 63 E y"R

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4 08i

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Attechment 3 I g o 1 (,

MN N

_x ,-a .,

~ ~ . ~ .

nt 3

' /WrloM G 4 - W;$h E rsumber o9 OPERAELE Channels leT.S 4ha:S lAtta _

A f equ'. I b 3ee H'.n'.murn OPE R ABL4 Channels per Tr;p (

)LS-88-042 Q Fv u + n reqv;rement,, place we ;noperate channe t in the +v:pped condit;on s.Ji+g;n 2Q hours. .

rage 30 of 42

~

nS a 3'~3.F 1 ( co r11 oiveW CONTROL ROD BLOCK INSTRUMENTATION TABLE NOTATIONS

  • With more than one control rod withdrawn. ilot applicable to control rods removed per Specification 3.9.10.1 or 3.9.10.2.

(a) This function shall be automatically bypassed if detector count rate is

> 100 cps or the IRM channels are on range 3 or higher.

(b) This function shall be automatically bypassed when the associated IRH channels are on range 8 or higher.

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

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

hours for re-(e) A channel may be placed in an inoperable status for up t quired surveillance provided at least,one other OPERABLE channel in the same trip function 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 required by the Minimum OPERABLE Channels per Trip Function requirement, place at least one inoperable channel in the tripped condition within I hour.

ACTION 62 - With the number of OPERABLE channels less than required by the Minimum OPEPABLE 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 - Vith the number of OPERABLE channels less than required by the Minimum OPERABLE Channels p: Trip Function requirement, initiate a rod block.

n m t uvme e rutt 1 1/4 3-65

. Attechmsnt 3 to U.602078 Page 14 of 16 Insert for par _e 3/4 3 65 ACTION 64 - With the number of OPERABLE channels less than required by the Minimum OPERABLE Channels per Trip Function requirement, verity within one hour that a sufficient number of channels remain OPERABLE to initiate a rod block by the associated Trip Function, and place at least one inoperabic channel in the tripped condition within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. O the tvi s e , initiate a rod block.

t b

i k

l

TABLE 4.3.6-1

~

n C- CONTROL ROD BLOCK INSTRUMENTATION SURVEILLANCE REQUIREMENTS

-5' E CitANNEL OPERATIONAL

.: CilANNEL CONDITIONS IN VillCII Cl{ANNEL FUNCTIONAL 6 OtECK TEST- CAllBRATION g

,) SURVE!LLANCE REQUIRED j -- TRIP FUNCTION g 1. ROD PATTERN CONTROL' SYSTEM

a. Low Power Setpoint HA S/U(b)(

- 0 RIII 1, 2 l g b .- RVL High Power Setpoint NA $/U

"(g)

"gc '

I ll 2.'APR){ . .

a. Flow Blased Neutron Flux -

Upscale NA S/U G SA 1 S/U ;M-Q , NA 1, 2, 5

b. Inoperative NA NA S/U d J SA' I
c. Downscale-
w. .d. Heutron Flux - Upscale, Startup~ NA. S/U(b)gO 'SA 2, 5 N 3. SOURCE RANGE MONITORS NA S/U ,W ' NA 2, 5
  • ' a. Detector not. f ull in - SA 2, 5 g b. Upscale NA S/U(b),W NA 2, 5
c. Ino' perative NA S/U(b),W NA S/U ,W SA 2, 5
d. Downstale
4. INTERMEDIATE RANGE MONITORS 2, 5
a. Detector not full in. NA S/U(b) ,W NA NA S/U ,W SA 2, 5
b. Upscale- 2, 5 HA
c. ' Inoperative NA ,S/U(b)*v - 2, 5
d. Downscale NA .S/U ,W -SA 5.'. SCRAM DISCHARGE VOLUME -2, 5*

S R II) 1

a. Water tevel-nigni
6. REACTOR COGLANT SYSTEM RECIRCULATION FLOW
a. Upscale NA S/U(b SA 1 .

na,ca. e. -e

7. REACTOR MODE SWITCH .

3,' 4 *3SX

a. Shutdown Mode. HA :R- NA
b. Refuel Mode- NA R NA 5 'M$$7

.o O~$n 2"?

E i, E =

., S E

' =>

Attachment 3 to tf-602078

. Page 16 of li Attachment 3 U-601871 1.5-P 8-04 2 Page 32 of 42 TABLE 4.3.6-1 (Continued) ,

CONTROL P00 BLOCK'lN5TRUl4ENTAT10N SURVEILLANCE Rt0VIRtHfHT5' TABLE NOTATIONS (a) Neutron detectors may be excluded from CHANNEL CALIBRATION.

(b) Vithin 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 7 days.

(c) Within one < orior to control rod movement, unless performed within the previot aours, and as each power range above the RPCS low power setpoint is .tered 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 power increase or decrease.

r , -- - , r-t) .

-"'-'-f^::-

" t 1;;.;; =U.s; p^^C

. . . c, s ovv.s u n e;: "._,'

. r , ., ;;.Ed :; . r n ' -Dg}g(gk .

(e) Includes reactor manual control multiplexing system input.

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

Vith any control rod withdrawn. Not appilcable to control rods removed per Specification 3.9.10.1 or 3.9.10.2.

CLlHTON - UNIT 1 ---3/4 3-69

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