Text

Proposed Tech Specs Instrumentation Associated W/High Pressure Core Spray Sys,Reactor Core Isolation Cooling Sys & Residual Heat Removal Sys
	ML20095G640
Person / Time
Site:	Clinton
Issue date:	12/14/1995
From:	; ILLINOIS POWER CO.
To:	;
Shared Package
ML20095G627	List: ML20095G640; U-602508, Application for Amend to License NPF-62,requesting Various Proposed Changes to TS for Instrumentation Associated W/High Pressure Core Spray Sys,Reactor Core Isolation Cooling Sys & Residual Heat Removal Sys;
References
	NUDOCS 9512210134
	Download: ML20095G640 (16)
	v • d • e

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' Attachment 3 to U-602508 NS-95-017 Page 1 of 9 Attached Marked-Up Pages of the Technical Specifications 1

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9512210134 951214 PDR ADOCK 05000461 P POR

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/AttacBment 3J to U-(Fp]Pl3Tpqh NS-95-017-Page 2 of 9

' * - ECCS Instrumentation 3.3.5.1 Table 3.3.5.1 1 (page 3 of 5)

Emergency Core Cooling system Instrumentation

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APPL!CASLE COND1TIONS H0 des OR , REFERENCED OTHER REQUIRED FROM CHANNELS PER REQUIRED SURVEILLANCE ALLOWABLE

- sPECIFIED

CONDITIONS FUNCTION- ACTION A.1' REQUIREMENTS 'VALUE FUNCTION

3. High Pressure Core spray (HPCs) system

a. Reactor vesset 1,2,3, 4(b) B SR 3.3.5.1.1 t -47.7 inches Water Level - Low sn 3.3.5.1.2 Low, Level 2 4(*),5(*) sR 3.3.5.1.3 SR 3.3.5.1.4 sR 3.3.5.1.5

b. Drywet t 1,2,3 4(b) a st 3.3.5.1.1 s 1.88 psig Pressure - High sR 3.3.5.1.2 st 3.3.5.1.3 sR 3.3.5.1.4 sa 3.3.5.1.5

c. Reactor Vesset 1,2.7 2 C SR 3.3.5.1.1 5 54.2 Inches Water sa 3.3.5.1.2 Level - High, 4(U he) sR 3.3.5.1.3 Level 8 sR 3.3.5.1.4 SR 3.3.5.1.5 7[ g l

RCIC storage Tank 1,2,3, 2 'D sR 3.3.5.1.1 t inches j L d.

Level - Low sR 3.3.5.1.<

4(c) $(c) sR 3.3.5.1.3 SR 3.3.5.1.4 sR 3.3.5.1.5 sR 3.3.5.1.1 s 12 inches

'f.I e. sypression Pool 1,2,3 2 .O k Water Level-High SR 3.3.5.1.2 sR 3.3.5.1.3 SR 3.3.5.1.4 SR 3.3.5.1.5

f. HPCs Punp 1,2,3, 1 E sR 3.3.5.1.1 1 120 psig Discharge SR 3.3.5.1.2 Pressure - High 4(*),5(*) sa 3.3.5.1.3 (Bypass) SR 3.3.5.1.4 sR 3.3.5.1.5

g. HPCs system Flow. 1,2,3, 1 E sa 3.3.5.1.1 t 500 gpa j Rate - Low sR 3.3.5.1.2 i sR 3.3.5.1.3 i

(gypass) 4(a) 5(a)

SR 3.3.5.1.4 SR 3.3.5.1.5

h. Manual Initiation 1,2,3, 1 C SR 3.3.5.1.5 NA 4(a) $(a)

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(continued)

(a) When associated subsystem (s) are required to be OPERA 8LE.

(b) Also required to initiate the associated dieset generator.

(c) When HPCs is OPERA 8LE for compliance with LCo 3.S.2, "ECCs -shutdown," and aligned to the RCIC storage tank while tank water levet is not within the limits of SR 3.5.2.2.

CLINTON 3.3-41 AmendmentNo.Ek

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NS 017 Page 3 of 9 RCIC System Instrumentation 3.3.5.2

.i Table 3.3.5.2-1 (page 1 o( D ,

Reactor Core Isolation Cooling system Instrunentation

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CONDITIONS

! REQUIRED REFERENCED CHANNELS PER FROM REQUIRE 0 SURVEILLANCE .ALLOWMLE REQUIREMENTS VALUE FUNCTION FUNCTION ACTION A.1' 4 8 SR 3.3.5.2.1 2 47.7 inches j

1. Reactor vesset Vater sR 3.3.5.2.2 Level-Low Low, Level 2 4

SR 3.3.5.2.3 sR 3.3.5.2.4 SR 3.3.5.2.5 2 c sR 3.3.5.2.1 s 52.6 inches i

2. Reactor vessel Water sR 3.3.5.2.2 j I Levet -High, Levet 8 sR 3.3.5.2.3 I sa 3.3.5.2.4 %g f

, j sR 3.3.5.2.5 sR 3.3.5.2.1 t inches j 2 . ,0

3. RCIC storage Tank st 3.3.5.2.2 I

J tevet - Low SR 3.3.5.2.3 ,

st 3.3.5.2.4 ,

sR 3.3.5.2.5 l

2 0 sR 3.3.5.2.1 5 -3 inches 1 4. s w ession Poot Water SR 3.3.5.2.2 Levet - Migh st 3.3.5.2.3 SR 3.3.5.2.4 sR 3.3.5.2.5 c SR 3.3.5.2.5 NA-

5. Marnal Initlation 1 1

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-CLINTON 3.3-47 AmendmentNo.M

,$ Attachment 3 to U-602508 NS-95-017

' Priaary Centainment and Drywell Isolat$$$ liistf umentation 3.3.6.1 Tabte 3.3.6.1 1 (page of Primary Contalrument and Drywett Isola loti Ins runentation APPLICASLE CON 0lTIONS MODES OR REQUIRED REFERENCE 0 OTNER CHANNELS FROM SPECIFIED PER REQUIRED SURVEILLANCE AllouA8tE FUNCTION CON 0lfl0NS FUNCTION ACfl0N F.1 REQUIREMENTS VALUE

1. Main Steam Line Isolation

a. Reactor Vesset Vater 1,2,3 4 G SR 3.3.6.1.1 2 -147.7 inches Level-Low Low Low, SR 3.3.6.1.2 Level 1 SR 3.3.6.1.3 ,

SP 3.3.6.1.5 SR 3.3.6.1.6 SR 3.3.6.1.7

b. Main Steam Line 1 4 N SR 3.3.6.1.1 1 837 pelg Pressure - Low SR 3.3.6.1.2 SR 3.3.6.1.3 SR 3.3.6.1.5 SR 3.3.6.1.6 SR 3.3.6.1.7

c. Main Steam Line 1,2,3 4 G SR 3.3.6.1.1 s 178 peld Flow - Nish SR 3.3.6.1.2 SR 3.3.6.1.3 SR~ 3.3.6.1.5 SR 3.3.6.1.6

. SR 3.3.6.1.7

d. Condenser Vectasa-Low 1,2("I, 4 C SR 3.3.6.1.1 1 7.6 inches SR 3.3.6.1.2 Ng vacuun 3(*) SR 3.3.6.1.3 SR 3.3.6.1.5 SR 3.3.6.1.6

e. Main Steam Tunnet 1,2,3 4 G SR 3.3.6.1.1 s 171*F Temperature - Nish 'SR 3.3.6.1.2 1

.SR 3.3.6.1.5 1 SR 3.3.6.1.6 j

f. Main Steam Line Turbine 1,2,3 4 C SR 3.3.6.1.1 Modules 1 4 j Sullding SR 3.3.6.1.2 s 142*F, j Temperature -Nigh SR 3.3.6.1.5 Module 5 1 SR 3.3.6.1.6 s 150*F

g. Manual Initiation 1,2,3 g *4 J SR 3.3.6.1.6 NA

)

(continued) I (a) With any turbine stop valve not closed. ,

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i CLINTON 3.3-55 AmendmentNo.>d l

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Pritary Centainment and 'Drywell Isolaticn Instrumentation 3.3.6.1

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Tabte3.3.6.11(page2of[p i Primary containment and crywett Isota I trumentation -

APPLICA8LE CON 01TIONs MODES OR REQUtRED REFERENCED OtNER CNANNELS FROM SPECIFIED PER REQUIRED SURVEILLANCE

ALLOWA8LE FUNCTION ACTION F.1 REQUIREMENTS VALUE FUNCTtod COMOITIONS

2. Primary Containment and Drywett isolation *

a. Reactor Vesset Water 1,2,3 4(b) g st 3.3.6.1.1 2 - 47.7 inches ,

Level-Low Lw, Level 2 st 3.3.6.1.2 i st 3.3.6.1.3 st 3.3.6.1.5 J st 3.3.6.1.6 (c) 4 0 st 3.3.6.1.1 i - 47.7 inches st 3.3.6.1.2 st 3.3.6.1.3 st 3.3.6.1.5 st 3.3.6.1.6

b. Drywell Pressure-Nigh 1,2,3 4(b) K SR 3.3.6.1.1 5 1.88 pelg st 3.3.6.1.2 l st 3.3.6.1.3 SR 3.3.6.1.5 st 3.3.6.1.6

c. Reactor Vesset Water 1,2,3 4 I st 3.3.6.1.1 t -47.7 inches.

Level-Low LN, SR 3.3.6.t.2 Level 2 (ECCs SR 3.3.6.1.3 Olvisions 1 and 2) sa 3.3.6.1.5 .,

SR 3.3.6.1.6

d. Drywett Pressure-Nigh 1,2,3 4(b) I st 3.3.6.1.1 5 1.88 psig (ECCS Olvisions 1 SR 3.3.6.1.2 and 2) st 3.3.6.1.3 st 3.3.6.1.5 SR 3.3.6.1.6

e. Reactor vessel Water 1,2,3 4 I SR 3.3.6.1.1 t 47.7 Inches' Level-Low Low', Levet SR 3.3.6.1.2 2 (NPCs NSPs Olv 3 and SR 3.3.6.1.3

4) st 3.3.6.1.5 st 3.3.6.1.6

f. Dryvett Pressure-Migh 1,2,3 4 I st 3.3.6.1.1 5 1.88 pelg (NPCs NsPs Div 3 and 4) SR 3.3.6.t.2 st 3.3.6.1.3 SR 3.3.6.1.5 SR 3.3.6.1.6 (continued)

(b) Also required to initiate the associated drywelt isolatlon function.

(c) During operations with a potentist for draining the reactor vesset.

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CLINTON 3.3-56 AmendmentNo.M l 1

$Nahmemnrvtsv-vgacm.;

NS-95-017

' Page 6 of 9 s . '

. Pricary C:ntainment and Drywall Isolation Instrumintation 3.3.6.1 b

Table 3.3.6.1 1 (page of[

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1 Primary containment and Drywett Isota I rumentation APPLICA8LE CONolTIONS MODES OR REQUIRED REFERENCE 0 OTHER CNANNEls FRCH

sPECIFIED PER REQUIRED SURVEILLANCE $LLOWASLE FUNCit0W CONDITIONS FUNCTION ACTION F.1 REQUIREMENTS valla! 4 l

l i

2. Primary Contaltunent and '

Drywell Isolation (continued)

s. Containment tullding (c),(d) 4 .N st 3.3.6.1.1 5 500 aft /hr fust Transfer Foot .

SR 3.3.6.1.2 Ventitation Plenus st 3.3.6.1.5 Radiatien- Nish sa 3.3.6.1.6

i

h. Containment Building 1,2,3 '4(b) I st 3.3.6.1.1 5 400 aft /hr -

Exhaust st 3.3.6.1.2 Radt atton - HIsh sa 3.3.6.1.5 SR 3.3.6.1.6 (c),(d) 4 N st 3.3.6.1.1 5 400 edt/hr st 3.3.6.1.2 st 3.3.6.1.5 sa 3.3.6.1.6

1. Containment Buttding 1,2,3 4(b) I st 3.3.6.1.1 s 400 mR/hr continuous containment st 3.3.6.1.2 Purge (CCP' Eshaust st 3.3.6.1.5

. Radiation - Nigh SR 3.3.6.1.6 (c),(d) 4 N st 3.3.6.1.1 s 400 sR/hr

> st 3.3.6.1.2 st 3.3.6'.1.5 SR 3.3.6.1.6

j. Reactor vessel Water 1,'2,3 4(b) I st 3.3.6.1.1 t -147.7 inches Levet -Low Lou Low, SR 3.3.6.1.2 Leve1 1 - st 3.3.6.1.3 sR 3.3.6.1.5 st 3.3.6.1.6 (c) 4 0 SR 3.3.6.1.1 t +147.7 inches st 3.3.6.1.2 st 3.3.6.1.3 st 3.3.6.1.5 SR 3.3.6.1.6

k. Containment Pressure- (e) 2 I st 3.3.6.1.1 5 3.0 psid Nlgh SR 3.3.6.1.2

$R 3.3.6.1.5 SR 3.3.6.1.6 L. Manual Initiation 1,2,3 2(b) J st 3.3.6.1.6 NA (c),(d) 2 N SR 3.3.6.1.6 NA (continued)

(b) Also required to Initiate the associated drywett isolation fav: tion.

(c) During operations with a potentist for draining the reactor vessel.

l (d) DurIng CORE ALTERATIONS and during movement of irradiated fuel assemblies in the primary or secondary contalrunent. l (e) MODES 1, 2, and 3 with the associated PCIVs not closed.

1 CLINTON 3.3-57 AmendmentNo.)W

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Attaciunest's to U-602508 ' "' ~

NS-95-017 Page 7 of 9 Prisary Centainm:nt and Drywell Isolaticn Instrumentation 3.3.6.1 Tat-te 3.3.6.1 1 (page 4 f I '

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Primary Contaltunent and Drywell Isolat natrumentation I

APPLICA8LE CON 0!TIONS MODES OR REQUIRED REFERENCED )

OTHER CHANNELS FROM l SPECIFIED PER REQUIRED SURVEILLANCE ALLOWA8LE l FUNCTION CON 0!TIONS FUNCTION ACTION F.1 REQUIREMENTS VALUE

3. Reactor Core Isolation (RCIC) system i

solohlonys wr i%:Idu.m

a. RCIC tteam Line 1,2,3 2 I sR 3.3.6.1.1 s 118.5 inches A Flow-High sR 3.3.6.1.2 water st 3.3.6.1.3 s2 3.3.6.1.5 s2 3.3.6.1.6

b. RCIC steam Line 1,2,3 - 2 I st 3.3.6.1.2 s 13 seconds Ftou - NIgh, st 3.3.6.1.5 Time Detey st 3.3.6.1.6

c. RCIC steam s g ply Line 1,2,3 2 I st 3.3.6.1.1 1 52 psig Pressure - Low SR 3.3.6.1.2 st 3.3.6.1.3 st 3.3.6.1.5 st 3.3.6.1.6

d. RCic Turbine Exhaust 1,2,3 4 I st 3.3.6.1.1 s 20 psig Diaphregn st 3.3.6.1.2 Pressure - NIsh SR 3.3.6.1.3 st 3.3.6.1.5 s st 3.3.6.1.6 i

e. RCic Equipment Room 1,2,3 2 I st 3.3.6.1.1 5 207'F Ambient SR 3.3.6.1.2 Teaperoture - NIsh SR 3.3.6.1.5 l sa 3.3.6.1.6

f. Maln steen Line Tunnet 1,2,3 2 I st 3.3.6.1.1 s 171*F Asblent st 3.3.6.1.2 Temperat se - High st 3.3.6.1.5 SR 3.3.6.1.6

g. Main steen Line Tunnet 1,2,3 2 I SR ~3.3.6.1.2 s 28 minutes Temperature Timer SR 3.3.6.1.5 SR 3.3.6.1.6

^

h. n -_ .. , ,. ne m s ...

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M.#6.1. __be4 /,/

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1.prya e.Il steam Line RCIC/RNR 1,2,3 2 I SR 3.3.6.1.1 s 188 inches g Flow - Nigh SR 3.3.6.1.2 water

SR 3.3.6.1.3 SR 3.3.6.1.5 SR 3.3.6.1.6 P

(continued)

CLINTON 3.3-58 Amendment No. )PI W -

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' ' , Attacho - i to U-602508

', NS-95-017 Page 8 of 9 Primary Containment and Dryweil Isolation Instrumentation 3.3.6.1 l

1 Table 3.3.6.1-1 (page 'of ) ]

Primary Contalrunent and Drywell Iso ( (off f trunentation l l

APPLICABLE CON 0!TIONs '

H00Es OR REQUIRED REFERENCE 0 OTNER CNANNEls FROM-

+

sURVE!LLANCE ALLOWABLE SPECIFIED PER REQUIRED REQUIREMENTS VALUE CONDITIONS FUNCTION ACTION F.1 FUNCTION

3. RCIC system Isolation (continued)

I sR 3.3.6.t.1 5 1.88 psig J. Drywett Pressure - 1,2,3 2 st 3.3.6.1.2 Nigh st 3.3.6.1.3 st 3.3.6.1.5 st 3.3.6.1.6

^

1,2,3 2 J st 3.3.6.1.6 NA

k. Manual Initiation

4. Reactor Water Cleanup (RWCU) system Isolation I st 3.3.6.1.1 5 66.1 spm

a. Differentist flow - 1,2,3 2 st 3.3.6.1.2 High st 3.3.6.1.5 ,

SR 3.3.6.1.6 I

I SR 3.3.6.1.2 5 47 seconds

b. Offferentist 1,2,3 2 l SR 3.3.6.1.4 Ftow-Timer SR 3.3.6.1.6 I SR 3.3.6.1.1 5 20$*F

c. RWCU Neat Exchanger 1,2,3 2 per room SR 3.3.6.1.2 Equipment Room SR 3.3.6.1.5 Temperature-Migh sa 3.3.6.1.6 I sR 3.3.6.1.1 5 202*F

d. RWCU Puy Rooms 1,2,3 2 per room SR 3.3.6.1.2 Temperature-Ninh sa 3.3.6.1.5 SR 3.3.6.1.6 1,2,3 2 1~ SR 3.3.6.1.1 5 171* F

e. Main steam Line Tunnel SR 3.3.6.1.?

Ambient Temperature- SR 3.3.6.1.5 Nigh sa 3.3.6.1.6 1,2,3 4 I sR 3.3.6.1.1 2 -47.7 inches

f. Reactor vesset Water SR 3.3.6.1.2 Level-Low Low, -

st 3.3.6.1.3 N

Levet 2 SR 3.3.6.1.5 SR 3.3.6.1.6 0 SR 3.3.6.1.1 t -47.7 inches (c) 4 sR 3,3.6.1.2 SR 3.L6.1.3 SR 3.3.i.1.5 SR 3.3.6.1.6 1,2 2 L SR 3.3.6.1.6 NA

g. sterxtry Liquid control system initiation 1,2,3 2 J sR 3.3.6.1.6 NA

h. Manual Initiation (c),(d) 2 N sR 3.3.6.1.6 NA (continued)

(c) During operations with a potential for draining the reactor vessel.

(d) During CORE ALTERATIONS and during movement of irradiated fuel asseablies in the primary or secondary contairnent.

3.3-59 AmendmentNo.g CLINTON

C Attachment 3 to U-602508 NS-95-017 s Page 9 of 9

~

Primary Containment and Drywell Isolation Instrumentation 3.3.6.1 i i

& .- l Table 3.3.6.1-1 (page of /5 A)

Primary Contairunent and Drywell Isola trunentation APPLICABLE CONDITIONS H0 des OR REFERENCED OTHER REQUIRED FROM SPECIFIED CHANNELS PER REQUIRED SURVEILLANCE

ALLOWA8LE FUNCTION CONolTIONs FUNCTION ACTION F.1 REQUIREMENTS VALUE

5. RHR system Isolotion

a. RHR' Heat Exchanger 1,2,3 2 per room I SR 3.3.6.1.1 s 160*F )

Aablent sR 3.3.6.1.2 Temperature - HIgh sR 3.3.6.1.5 SR 3.3.6.1.6

b. Reactor vesset Water 1,2,3(f)~ 4 I sR 3.3.6.1.1 t 8.3 inches !

Level - Low, Level 3 st 3.3.6.1.2 l

. sa 3.3.6.1.3 l sR 3.3.6.1.5 l sR 3.3.6.1.6 l

c. Reactor vessel Vater 3C8), 4,5 4(h) M sa 3.3.6.1.1 1 8.3 Inches 4 Level - Low, Level 3 sR 3.3.6.1.2 l sR 3.3.6.1.3 l SR 3.3.6.1.5 I SR 3.3.6.1.6

d. Reactor vessel Vater 1,2,3 4 I sR 3.3.6.1.1 2 -147.7 i SR 3.3.6.1.2 inches l Level - Low Low Low, Levet 1 SR 3.3.6.1.3 SR 3.3.6.1.5 SR 3.3.6.1.6 60

e. Reactor vessel 1,2,3 4 I sR; 3.3.6.1.1 sJ5epsig j Pressure - High SR 3.3.6.1.2 '

SR 3.3.6.1.3 sR 3.3.6.1.5 SR 3.3.6.1.6

f. Drywel1 Pressure-High 1,2,3 8 I SR 3.3.6.1.1 s 1.88 psig SR 3.3.6.1.2 SR 3.3.6.1.3 SR 3.3.6.1.5 sR 3.3.6.1.6

g. Manual Initiation 1,2,3 2 J sR 3.3.6.1.6 NA (f) Vith reactor steam dome ,>ressure greater than or equal to the RHR cut in permissive pressure.

(g) Vith reactor steam dome pressure tess than the RHR cut in permissive pressure.

(h) only one trip system required in MODES 4 and 5 with RHR shutdown Cooling systen Integrity maintained.

CLINTON 3.3-60 AmendmentNo.[

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! to U-602508 NS-95-017 Page1 of7 1

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2,, #+ . .t. ,_r.. Attachment 4 to U .692508 NS-95-017 l

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Page 2 of 7 Primary Containment and Drywell Isolation Instrumentation B 3.3.6.1 r

e BASES ,

APK ICABLE 2.k. Containment Pressure-High (continued)

SAFETY ANALYSES, .

LCO, ud The Allowable Value was chosen to prevent opening of the APPLICASILITY containment ventilation supply and exhaust isolation bypass valves when excessive differential pressure could result in damage to the associated ductwork.

Two channels of the Centainment Pressure-High Function are available and are required to be.0PERABLE to ensure that no single instrument failure can preclude the isolation function.

2 .1. Manual Initiation The Manual Initiation push button channels introduce signals into the primary containment and drywell isolation logic that are redundant to the automatic protective instrumentation and provide manual isolation capability.

There is no specific USAR safety analysis that takes credit for this Function. It is retained for the isolation function as required by the NRC in the plant licensing basis.

There are two push buttons for the logic, one manual ~

initiation push button per trip system (i.e., IB21H-525A and 1821H-5258). There is no Allowable Value for this Function since the channels are mechanically actuated based solely on the position of the push buttons.

Two channels of the Manual Initiation Function are available and are required to be OPERABLE. This function is also required to be OPERABLE during CORE ALTERATIONS, movement of irradiated fuel assemblies in primary or secondary containment, or OPDRVs. This Function initiates isolation of valves which isolate primary containment penetrations which bypass secondary containment. Thus, this Function is -

also required under those conditions in which secondary containment is required to be OPERABLE.

- A.Jkrictor iln Coolina System Isolation

- 6 )

3.a.p.Le7 %iN/qA RCIC Steam Line flow-Hiah SmiMln

)d'(*,IRCICSkeamLine ow-High Function is provided to detect a I break o th C steam lines and initiates closure of the s ine isolation valves. If the steam is allowed to continue flowing out of the break, the reactor will (continued) /

CLINTON B 3.3-148 Revision No. g

NS-95-017 4

Page 3 of 7 Primary Containment and Drywell Isolat.icn Instrumentation B 3.3.6.1 BASES APPLICABLE a. I e Flow-Hiah (continued)

SAFETY ANALYSES, \ gn LCO, and depressurize and core uncovery can occur. Therefore, the APPLICABILITY isolation is initiated on high flow to prevent or minimize

-- core damage. The isolation action, along with the scram function of the Reactor Protection System (RPS), ensures that the fuel peak cladding temperature remains below the limits of 10 CFR 50,46. Specific credit for this Function is not assumed in any USAR accident analyses since the bounding analysis is performed for large breaks such as ,

recirculation and MSL breaks. However, these instruments pr steam line bre from becoming bounding.

WSsty%fM AusSey aC ine Flow- i s w M.61ated from t - ansmitters that cted to the system steam M hds 'Two channels Steam Line Flow-High Functions

_[ are l1able and are quired to be OPERABLE to ensure that single instrument failure can preclude the isolation M N 49dIMy function.

841/Un3 The Allowable Value is chosen to be low enough to ensure that the trip occur to prevent fuel damage and maintains

, :.g the HSLB event as the bounding event.

( )

3.b. RCIC Steam line Flow-Hiah Time Delay The RCIC Steam Line Flow-High Time Delay is provided to prevent false isolations on RCIC Steam Line Flow-High during system startup transient: and therefore improves system reliability.' This Function is not assumed in any i USAR transient or accident analyses.

The Allowable Value was chosen to be long enough to prevent false isolations due to system starts but not so long as to impact offsite dose calculations.

Two channels for RCIC Steam Line Flow-High Time Delay Functions are available and are required to be OPERABLE to ensure that no single instrument failure can preclude the isolation function.

3.c. RCIC Steam Supp1v Line Pressure-Low Low RCIC steam supply line pressure indicates ~ that the pressure of the steam may be too low to continue operation of the RCIC turbine. This isolation is for equipment protection and is not assumed in any transient or accident i

analysis in the USAR. However, it also provides a diverse (continued)

CLINTON B 3.3-149 Revision No. J4

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' Page 4 of 7 Primary Containment and Drywell isolation Instrumentation B 3.3.6.1 e

BASES APPLICABLE 3.c. RCIC Steam Supply Line Pressure-Low (continued)

SAFETY ANALYSES, LCO, and signal to indicate a possible system break. These APPLICABILITY instruments are included in the' Technical Specifications (TS) because of the potential for risk due to possible failure of the instruments preventing RCIC initiations.

The RCIC Steam Supply Line Pressure-Low signals are initiated from two transmitters that are connected to the-

system steam line. Isolation of the RCIC vacuum breaker

" isolation valves requires RCIC Steam Supply Line Pressure-Low coincident with Drywell Pressure-High signals. Two channels of RCIC Steam Supply Line Pressure-Low Functions are available and are required to be OPERABLE to ensure that no single instrument failure can preclude the isolation function.

The Allowable Value is selected to be high enough to prevent damage to the system turbine.

3.d. RCIC Turbine Exhaust Diaphraam Pressure-Hiah High turbine exhaust diaphragm pressure indicates that the (}

pressure may be too high to continue operation of the associated system turbine. That is, one of two exhaust

' diaphragms has ruptured and pressure is reaching turbine- I casing pressure limits. This isolation is for equipment l protection and is not assumed in any transient or accident analysis in the USAR. These instruments are included in the TS because of the potential for risk due to possible failure of the instruments preventing RCIC. initiations (Ref. 3).

The RCIC Turbine Exhaust Diaphragm Pressure-High signals are inititted from four transmitters that are connected to

the area between the rupture diaphragms on each system's turbine exhaust line. Four channels of RCIC Turbine Exhaust Diaphragm Pres.sure-High Functions are available and are required to be OPERABLE to ensure that no single instrument failure can preclude the isolation function.

The Allowable Values are low enough to prevent damage to the sy

e.

3 e ient Temperature-High h peratures are provided to detect a leak from !

the associated system steam piping. The isolation occurs when a very small leak has occurred and is diverse to the (continued)

CLINTON B 3.3-150 Revision No. N

- ~ . . . _ .

. s' Attachment'4 to'U-602508 O . NS-95-017 o - Page 5 of 7 Primary Containment and'Drywell Isolation Instrumentation B 3.3.6.1 BASES APPLICABLE 3 ,

Mient Temperature-High (continued) 2 SAFETY ANALYSES,-

LCO, and higY ow instrumentation. If the small leak is allowed to APPLICABILITY continue with.out isolation, offsite dose limits may be reached. These Functions are not assumed in any USAR transient or accident analysis,'since bounding analyses are perfor ned for large breaks such as recirculation or MSL breaks.

Ambient Temperature-High signals are initiated from thermocou at are app located to protect the system a ored. Two struments monitor each ar a.'y%, ischannelbe - or M&end IC Ambient Tempera e- un on av ale and are ramdred to D PERABLE to ensure that no si ailure can rec y "gm @@a,,(n _ , 7 f..

............,._....r.

. . _ _ _y , . _ , m . . . g

...g

_- _.......m.

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The Allowable Values are set low enough to detect a leak equivalent to 25 gpm.

3.f. Main Steam Line Tunnel Ambient Temperature-Hioh Ambient Temperature-High is provided to detect a leak in the RCPB and provides diversity to the high flow instrumentation. The isolation occurs when a very small leak has occurred. If the small leak is allowed to continue without isolation, offsite limits may be reached. However, credit for these instruments is not taken in any transient or accident analysis in the USAR, since bounding analyses are performed for large breaks such as MSLBs.

Ambient temperature signals are initiated from thermocouples located in the area being. monitored. Two channels of Main Steam Tunnel Tempe, ature-High Function are available and are required to be OPERABLE to ensure that no single instrument failure can preclude the isolation function.

Each Function has one temperature element.

The Allowable Values are chosen to detect a leak equivalent to 25 gpm.

(continued)

CLINTON 8 3.3-151 Revision No. /

. y' - ,.

.sv -- Attachment.4 to U.602508 O ,

NS-95-017 o .

Page 6 of 7 Primary Containment and Drywell Isolation Instrumentation B 3.3.6.1

,5 8

BASES APPLICABLE 3.a. Main Steam Line Tunnel Temperature Timer SAFETY. ANALYSES, LCO, and The Main Steam Line Tunnel Temperature Timer is provided to APPLICABILITY allow all the other systems that may be leaking in the main (continued) steam tunnel (as indicated by the high temperature) to be isolated before RCIC is automatically isolated. This ensures maximum RCIC System operation by preventing isolations due to leaks in other systems.. This Function is not assumed in any USAR transient or accident analysis; however, maximizing RCIC availability is an important F function.

Two channels for RCIC Main Steam Line Tunnel . Timer Function are available and are required to be OPERABLE to ensure that

~

no single instrument failure can preclude the isolation function.

The Allowable Values are based on maximizing the

. availability of the RCIC System; that is, providing sufficient time to isolate all other potential leakage sources in the main steam tunnel before RCIC is isolated.

3.1.fAYCI NSte m Line Flow-Hiah eam line flow is provided to detect a break br7we.1\ -t RCICMh of the on steam line of RCIC and RHR and initiates re of the isolation valves for both systems. If the steam were allowed to continue flowing out of the break, the reactor would depressurize and the core could uncover.

Therefore, the isolation is initiated at high flow to prevent or minimize core damage. Specific credit for this Function is not assumed in any USAR accident or transient analysis since the bou sis is performed for large breaks such as recir ation and L breaks. However, instrument _s prevent RCIC te m line break f dg b ming bo ng. hepDr7wsH ley heir (I st m line flow signals are initi ed ffrom ansmitter at are connected to the steam 1 ne d T cha are available and required to be OPE o ensure that no single instrument failure can preclude the isolation function. The Allowable Value is selected to ensure that the trip occurs to prevent fuel damage and maintains the MSLB as the boundary event.

(continued) i CLINTON B 3.3-152 Revision No.,,Vf'

Attachment 4 to U-602509 i'( - NS-95-017 7 f

- Primary Containm:nt and Drywell IsolaD8n Instrumentation B 3.3.6.1 BASES APPLICABLE 5.e. Reactor Vessel Pressure - Hiah l SAFETY ANALYSES, ;

LCO, and The Shutdown Cooling System Reactor Vessel Pressure-High APPLICABILITY Function is provided to isolate the shutdown cooling portion (continued) of the RHR System. This interlock (RHR cut in permissive) is provided only for equipment protection to prevent an intersystem LOCA scenario and credit for the interlock is not assumed in the accident or transient analysis in the 1 USAR.

The Reactor Vessel Pressure-High signals are initiated from four transmitters. Four channels of Reactor Vessel Pressure - High Function are available and are required to be OPERABLE to ensure that no single instrument failure can preclude the isolation function. The Allowable Value was chosen to be low e ^t :t u e system equi m .i i- !

" q,e n uri-s . A AoWonally determinal Alue o'n clu ds5 conservaNsons N cossure ure ejes/es of fhe Allowal1 of H,e RHR ShuNewn Cont /n S s te os, su s tle n do/ anon uain$ r (ter2.foos 1 5.f. Drvue ress e- ah asd IE/2 foot) consisten t With Us

*I'**"ents af NJC Gsserie lefler81/0. 1 High drywell pressure can indica reax irr tne ~'RC"B. Tha _ _ )

isolation of some of the PCIVs on high drywell pressure supports actions to ensure that offsite dose limits of 10 CFR 100 are not exceeded. The Drywell Pressure-High Function associated with isolation of the RHR System is not modeled in any USAR accident or transient analysis because other leakage paths (e.g., MSIVs) are more limiting.

High drywell pressure signals are initiated from pressure transmitters that sense the pressure in the drywell. Four channels of Drywell Pressurc-High Function are available and are required to be OPERABLE for isolation of the RHR test return lines to ensure that no single instrument failure can preclude the isolation function. In addition, four channels of Drywell Pressure-High Function are available and are required to be OPERABLE for isolation of the Fuel Pool Cooling Assist mode to ensure that no single instrument failure can preclude the isolation function.

The Allowable Value was selected to be the same as the ECCS Drywell Pressure-High Allowable Value (LC0 3.3.5.1), since this may be indicative of a LOCA inside primary containment.

(continued)

CLINTON B 3.3-161 RevisionNo.g

ML20095G640

Text

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