ML17277B743

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Proposed Tech Specs,Eliminating High Drywell Pressure Signal from Automatic Depressurization Sys Initiation Logic,Thereby Making Automatic Depressurization Sys & Low Pressure ECCS Qualified as High Pressure Sys
ML17277B743
Person / Time
Site: Columbia 
Issue date: 05/16/1985
From:
WASHINGTON PUBLIC POWER SUPPLY SYSTEM
To:
Shared Package
ML17277B742 List:
References
NUDOCS 8505220031
Download: ML17277B743 (10)
v • d • e


Text

TRIP FUHCTIOtt TABLE 3.3.3-1 EHERGEHCY CORE COOLlttG SYSTEH ACTUATION IHSTRUHEttTATIOH tel ttIHUH OPERABLE APPLICABLE CIIANllELS Pg)

OPERATIONAL TRIP SYSTEH COHDITIOHS ACTION A.

DIVISIOtt I TRIP SYSTEH

1. 'IIR-A LPCI HODE tt LPCS SYSTEH 2.

a.

Reactor Vessel Mater Level - Low Low Low, Level 1

2 b.

Drywell Pressure

- ttigh 2

c.

LPCS Pump Discharge Flow-Low (lffpimum Flow) 1 d.

Reactor Vessel Pressure-Low (IF+Perm)salve) 1 e.

Reactor Vessel Pressure-Low (LPCI $'pre ssive) 1 I

.LPCI Pump A Start Time Delay Relay Oy/~

1 g.

LPCI Pump A Discharge Flow-Low (Hinimum low(%

1 h.

Hanual Initiation

<<g I/dtvisfoo AUTOHATIC DEPRESSURIZATIOH SYSTEH TRIP SYSTEH "A"8 a.

Reactor Vessel Mater Level - Low Low Low, Level 1

2 ADS Timer 1

Reactor Vessel Mater Level - Low, Level 3'(Permissive) 1 LPCS Pump Discharge Pressure-ttigh (Pump Running) 2 LPCI Pump A Discharge Pressure-High (Pump Running) 2 Hanual Initiation 2/division lw4< bi+

P daV Laloh b X c 8 J

P'g 1, 2, 3, 1; 2, 3, 1, 2, 3, l, 2, 3, 4A 5*

1R 2R 31 1, 2, 3; 1; 2, 3, 1, 2, 3 1, 2, 3

1, 2, 3

I,2.,3 4A 5)R 3O 30 4A 5*

31 32 33 32 33 4*

5A 32 4A 5A 31 4A 5A 34 30 32 32 32 32 35 35 PDR

~ 8>05>S p

R ADDCK OS000397 PDR

TABLE 3.3.3-1 (Continued)

EHERGTEHCY CORE COOLING SYSTEH ACTUATIOtl INSTRUHEtlTATIOH TRIP FUNCTION B.

DIVISION 2 TRIP SYSTEH 1.

RIIR B and C

LPCI HODE HltllHUH OPERABLE APPLICABLE CtlANNELS Pg)

OPERATIONAL

,,,N)

ACTIOH C:

M a.

Reactor Vessel Mater Level - Low Low Low, Level 1 b.

Drywell Pressure

- lligh c.

Reactor Vessel Pressure-Low (LPCI Permissive) d.

LPCI Pump B Start Time Delay Relay e.

LPCI Pump OIscharOe Flow-Low (Hlolmum Flow) ~Q f.

Hanual Initiation 2.

AUTOHATIC OEPRESSURITATIOII SYSTEH TRIP SY

+O"P 2

2 1/val ve 1

1/pump 1/division 1R 2R 3O 1, 2, 3, 1, 2, 3, 3A 4 A 5

IS(

5RR 4 A 522(

4* 5'0 30 32 33 32 31 34 a ~

b ~.

c A.

Q e.

Reactor Vessel Water Leuel - LogCg ow, ADS Timer

~

~

Reactor Vessel Mater Level - Row, Level 3

LPCI Pump B and C Discharge Pressure-Nigh (Pump Running)

Hanual Initiation Ihkikt>

Level 1

2 1

(Permissive) 1 2/pump 2/division

~

~

~

Iy CfvfsfoF lo 2O'3 1, 2, 3

1, 2, 3

lq>~Z 30 32

'32 32 35

Oy I

'h

M TABLE 3.3.3-2 EHERGENCY CORE COOLING SYSTEH ACTUATION INSTRUHENTATION SETPOINTS TRIP FUNCTION TRIP SETPOINT ALLOWABLE VALUE Cn EAR CI A.

DIVISION 1 TRIP SYSTEH 1.

RllR-A LPCI NODE AND LPCS SYSTEH 1

a.

Reactor Vessel Mater Level - Low l.ow Low, Level 1

> -129 inches" b.

Drywell Pressure - High

< l.65 psig c.

LPCS Pump Discharge Flow-Low (Hinimum Flow)

> 770 gpm d.

Reactor Vessel Pressure-Low

~

y.

> 470 psig, (LPCS Permissive) lP Q decreasing e.

Reactor Vessel Pressure-l.ow

> 470 psig, (LPCI Permissive) j decreasing f.

LPCI Pump A Start Time Delay Relay Qg ~< 5 seconds g.

LPCI Pump A Discharge Flow-Low (Hlnimum F 1ow)'/hg9 gPm h.

Hanual Initiation 2.

AUTOMATIC OEPRESSURIIATIOM SYSTEII TRIP SYSTEM "A"

> -136 inches

< 1.85 Psig

< 900 gpm

> 450 psig, decreasing

> 450 psig, decreasing

< 6 seconds

> 650 gpm N.A.

a ~

C

+.'eactor Vessel Water Level - Low Low Low, Level 1

ADS Timer Reactor Vessel Water Level-Low, Level 3

(Permissive)

LPCS Pump Discharge Pressure-lligh (Pump Running)

LPCI Pump A Discharge Pressure-lliglr (Pump Running)

Hanual Initiation ln 4'LE'+

> -129 inches"

< 105 seconds

> 13.0 inches"

> 145 psig, increasing

> 125 psig, increasing lt.A.

N.a.

> -136 inches

< 117 seconds

> ll inches 125 psig, increasing

> 115 psig, increasing H.A.

~y Oy

'I lg II I

If

TABLE 3.3.3-2 (Continued)

EHERGENCY CORE COOLItIG SYSTEH ACTUATION INSTRUHENTATION SETPOINTS TRIP FUtICTION D.

D1VISION 2 TRIP SYSTEH 1.

RIIR 8 AtID C LPCI HODE TRIP SETPOltlT ALLOMABLE VALUE 2.

> 125 psig, increasing N.A.

1rthl hi+ sw itc.k.

a.

Reactor Vessel Mater Level - Low Low Low, Level 1

> -129 inches~

b.

Drywall Pressure - lligh

< 1.65 psjg c.

Reactor Vessel Pressure-Low (LPCI Permissive)

>41 g,

sing d.

LpCI Pomp 0 Start Time Relay Relay S+secoeda e.

LPCI Pump Discharge Flow-Low (Hinimum Flow)

~ ~ 800 Rpm f.

Hanual Initiation AUTOHATIC DEPRESSURI2ATIOH SYSTEH TRI H "8" a.

Reactbr Vessel Mater Level -QrO ow Low, Level 1

> -129 inches"

-lr D~e-I-1-Pressure=tI-i-rgr-ADS Timer

< 105 seconds c 6.

Reactor Vessel Mater Level-Low, Level 3

(Permissive)

> 13.0 inches" d e:

LPCI Pump 8 and C Discharge Pressure-lligh (Pump Running)

Hanual Initiation

> -136 inches

< 1.85 psig

> 450 psig, decreasing

< 6'seconds

> 650 gpm N.A.

> -136 inches

.85-ps4}t-

< ll7 seconds

> ll inches

> 115 psig, increasing N.A.

~y

TABLE 4.3.3.1-1 EHEAGEttCY CORE COOLlttG SYSTEH ACTUATION INSTAUHEt<TATION SURVEILLANCE RE UIAEHENTS TRIP r

A.

g'AR AARI FUttCT ION DIVISION I TRIP SYSTEH l.

Rlllt-A LPCI NODE AND LPCS SYSTEH a.

eactor Vesse Water Level-Low Low Low, Level 1

b.

Drywell Pressure

- High c.

LPCS Pump Discharge Flow-Low (Hinimum Flow) d.

Reactor Vessel Pressure-Low (LPCS Permissive) e.

Reactor Vessel Pressure-Low (LPCI Permissive) f.

LPCI Pump A Start Time Delay Relay g.

LPCI Pump A Flow"Low (Hinimum Flow) h.

Hanual Initiation 2.

AUI'OHATIC OEPAESSUAIZATIOtt SYSTEH CitANNEL CHECK CttnNNEL FUNCTIONAL TEST S

N.A.

N.A.

H

<<<<.A.

4 H.A..

R Cg 1, 2, 3, 4*

5*

R tt.A.

1, 2, 3, 4*, 5" 1, 2, 3, 4*, 5" 1, 2, 3, 4", 5+

1, 2, 3, 4", 5" 4a OPERATIONAL CttANttEL CONDITIONS FOR Wt!IClt CALIBRATION SURVEI Lt.ANCE RE UIRED TRIP SYSTEH

<<<<A<<<<lt a.

Reactor Vessel Water Level-Low Low Low, Level 1

e<<tee<<<<-Aeeeeeee

<<<<<<<<<<A-ADS Timer c

d; Reactor Vessel Water Level-Low, Level 3 (Permissive) d e.

LPCS Pump Oischae ge Pressure-ttigh (Pump Running)

+.

LPCI Pomp A Discharge Pressure-ttigh (Pump Running)

P ~.

Hanual Initiation I n 4 E 4 l +

zGo I+c k S

Ht-.A-.

N.A.

N.A.

tt. A.

N.A.

N.A.

H H

R N.A.

N.R-1, 2, 3

1, 2, 3

1, 2, 3

1, 2, 3 1,2,3 l, X)3

~y

(

N 0

ly 4

NI

TABLE 4.3.3. l-l (Continued)

EHERGENCY CORE CODLING SYSTEH ACTUATION INSTRUHEHTATIOH SURVEILLANCE RE UIREHENTS CI gl I

M WI Col 4ll TRIP FUNCTION 8;

DIVISION 2 TRIP SYSTEH 1.

RHR 8 AND C LPCI NODE CHANNEL CHECK CIIANNEL FUNCTIONAL TEST a.

Reactor Vessel Mater Level "

Low Low Low, Level 1

h.

Drywall Pressure - High c.

Reactor Vessel Pressure-Low (LPCI Permissive) d.

LPCI Pump 8 Start Time Delay Relay e.

LPCI Pump Discharge Flow-Low (Ninimom Flow) f.

Hanoal Initiation S

H N.A.

H N.A.

H +9

>LA.

N.A.g+

8 2.

AUTOHATIC OEPRESSURIZATIOH SYSTEH TRIP SYSTEH 48"8 CIIAHHEL CALIBRATION R

N.A.

OPERATIONAL CONDITiONS FOR WHICH IP 1,. 2, 3, 4", 5" 1, 2, 3

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

2 3

4" 5"

I a.

b.m d.m e.&

Reactor Vessel Mater Level-Low Low Low, Level 1 M

ADS Timer Reactor Vessel Water Level-Low, Level 3 (Permissive)

LPCI Pomp 8 and C Discharge Pressure-High (Pump Running)

Hanual Initiation S

H N.A.

H N.A.

N.A.

R N.A.

1, 2, 3

1, 2, 3

1, 2, 3

1, 2, 3

1, 2, 3

P in+ bit smite,k Pl Iv. A, l~>g 3

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