ML20094P537

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Proposed TS Table 3.3.2-3 Re Isolation Actuation Sys Instrumentation Response Time
ML20094P537
Person / Time
Site: Fermi DTE Energy icon.png
Issue date: 03/27/1992
From:
DETROIT EDISON CO.
To:
Shared Package
ML20094P518 List:
References
NUDOCS 9204080201
Download: ML20094P537 (11)
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Text

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

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ENCLOSURE 3 - PART 1 PROPOSED TECHNICAL SPECIF1d TION PAGE MARKUPS

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9204000201 920327 PDR ADO::K 05000343 P

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TABLE 3.3.1-2 REACTOR PROTECTION SYSTEM. RESPONSE TIMES

'm b

RESPONSE TIMr, FUNCTIONAL UNIT

-(Seconds 1 _

e E

1.

Intermediate Range Monitors:

NA a.

Neutro. Flux - High NA b.

Incperative 2.

Average Power Range Monitor *:

a.

Neutron Flux - High, Setdown NA b.

Flow Biased Simulated Thermal Power - High 6 i 1**

,V c.

Fixed Neutron Flux - High

< 0.09 RA d.

Inoperative 3.

Reactor Vessel Steam Dome Pressure - High

< 0.55 #

4.

Reactor Vessel Low Water Level - Level 3 7 1.05 :/F 5.

Main Steam Line Isolation Valve - Closure 2 0.06 q

6.

Main Steam Line Radiation - High RA NA a

7.

Drywell Pressure

.High 8.

Scram Discharge Volume Water Level - High NA a.

Flcat Switch NA b.

Level Transmitter

< 0.06 9.

Turbine Stop Valve - Closure

10. Turbine Control Valve Fast Closure 2 0.08***
11. Reactor Mode Switch Shutdown Position RA NA
12. Manual Scram g
13. Deleted m

E R

E

  • Neutron detectors are exempt from response time testing. Response tir: shall be measured -

from the detector cutput or from the input of the first electronic component in the channel.

    • Including simulated thermal power time constant.

p

'N

      • Measured from deenergization of K-37 relay which inputs the turbine control va;;e closure signal O

to the RPS.

Is sumera ATGD WPcm REWtitsc TsuG T&GrrrJG Tct1 rat RPS c rouds %.

SCSNMSC D tAE

$ Stu50L TE *iTa u G ANb 4tiufcEA1As(6 To THE AbemtJATRAfavE uM5

o R. TM RE M A,Nst/6 - CHAMNEL s o fL r.;D e sc TRt P t16JiT A kib TlELtw L.o Gif A ft6. KCf.J.is ECD.

TABLE 3.3.2-3 ISOLATION ACTUATION SYSTEM INSTRUMENTATION RESPONSE TIME

')

TRIP FUNCTION RESF0NSE TIME'(Seconds)#

1.

PRIPMY CONTAINMENT ISOLATION a.

reactor Vessel Low Water Level N

1)

Level 3 2)

Level 2 3)

Level 1 6 /,0+ ##.Are*/[M b.

Drywell Pressure - High g FNA c.

Main Steam Line 0)

NN 1

Radiation - High N I'

?.

Pressure - Low 40,S*#7.p u NA 3

flow - High 14 d.

Main Steam Line Tunnel Temperature - High NA e.-

Condenser Pressure

_High NA f.

Turbine Bldg. Area Temperature - High NA g.

Deleted d,

h.

Manual Initiation NA 2.

REACTOR WATER CLEANUP SYSTEM ISOLATION

)s a.

A Flos - High NA

,7 b.

Heat Exchanger / Pump /High Energy Piping Area Temperature - High NA c.

Htat Exchancer/ Pump / Phase Separator

,M, Area Ventilation Temperature AT - High NA

d. -

SLCS Initiation NA e.

Reactor Vessel Low Water Level - Level 2 p3NNk l

f.

Deleted g.-

Manual Initiation EA 3.

REACTOR CORE ISOLATION COOLING SYSTEM ISOLATION a.

RCIL Steam Line Flow - High

  1. NA b.

RCIC Storm Supply Pressure - Low J8 NA

)

c.

RCIC Turbine Exhaust Diaphragm Pressure - High NA d.

RCIC Equipment Room Temperature - High NA e.

Manual Initiation NA

);

FERMI - UNIT 2 3/4 3-18 Amendment No. 21, Ih

.. j

TABLE 3.3.2-3 (Continued)

)

ISOLATION ACTUATi')N SYSTEM INSTRUMENTATION RESPONSE TlHE TRIP FUNCTION RESPONSE T1HEfSeconds)#

4.

HIGH PRESSURE COOLANT INJECTION SYSTEM ISOLATION

[ MANb a.

HPCI Steam Flow - High b.

HPCI Steam Supply Pressure - Low c.

HPCI Turbine Exhaust Diaphragm Pressure - High ha d.

HPCI Equipment Room Temperature - High NA e.

Manual Initiation NA 5.

RHR SYSTEM SHUTDOWN COOLING MODE ISOLATION a.

Reactor Vessel Low Water Level - Level 3 NA b.

Reactor Vessel (Shutdown Cooling Cut-in Permissive Interlock) Pressure - High NA c.

Manual Initiation NA b

6.

SECONDARY CONTAINMENT ISOLATION Reactor Vessel 1.ow Water Level - Level 2 313W M a.

Fuel Pool Ventilation Exhaust Radiation - High(b) g$13M

/.

Drywell Pressure - High b.

)-NA c.

d.

Manual Initiation NA j

DCL61ED j

(a) 4,9,_fselation system-instrumentet4en rcese-t4*e-sham-be-measured-and-

-recorded a: ; part-of-th-ISOL4rT40N-SYSTEM-RE-SP0EE-T4ME.

I-solat4on-system instrumentation response time :pecified twTudes diesel generater

.-st:rting and ;cquence-leading-delay;.

(b) Radiation detectors are exempt from response time testing.

Response time shall be measured from detector output or the input of the first electronic component in the channel.

  • Isolation system instrumentation response time for MSIVs only.

No diesel grarator delays assumed for MSIVs.

S huiciivo synm innru.ent&tica rmon;; time for ;;;cciated valve l

-execpt MSI %

UIsolation system instrumentation response time specified for the Trip Function actuating each valve group shall be added to isolation time shown

'in Table 3.6.3-1 and 3.6.5.2-1 for valves in each valve group to obtain ISOLATION SYTMEM RESPONSE TIME for each valve.

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10sm7 -

3./. / '~

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FERMI - UNIT 2 3/4 3-19 AmendmentNo.Aj l

7%w-Twt ag 3 Y 3 -19 f

Anw Sensor is eliminated from response time testieg for the MSIV actuarfon logic circuits. Response time testing and conformance to the administrative limits for the remaining channel including trip unit and relay logic are required.

Response time testing is eliminated for the radiation loops based on the qualified Log Rad Monitors.

E JABLE 3.3.3-3 EMERGENC1.00RE COOLING SYSTEM RESPONSE TIMES RESPONSE TIME TRIP FUNCTION LSecondsl 1.

CORE SPRAY SYSTEM a.

Reactor Vessel Low Water Level - Level 1

< 30 $

b.

Drywell Pressure - High 7 30 #

c.

Reactor Steam Dome Pressure - Low-HA*

d..

Manual Initiation NA 2.

LOW PRESSURE COOLANT INJECTION MODE OF RHR SYSTEM a.

Reactor Vessel Low Water Level - Level 1

< 55 *F t.

Drywell Pressure - liigh 7 55 $P

/

c.

Reactor Steam Dome Pressure - Low HA*

d..

Reactor Vessel Low Water Level - Level 2 NA e.

Reactor Steam Dome Pressure --Low NA f.

Riser Differential Presa re - High NA g.

Recirculation Pump Differential Pressure -

NA High h.

Manual Initiation NA 3.

HIGH' PRESSURE COOLANT 'INJECTipN SYSTEM a.

Reactor. Vessel Low Water Level - Level 2

< 30 f

-lj b.

Drywell Pressure - High RA c.

Condensate Storage Tank Level - Low NA d.

Reactor Vessel Water Level High, level 8 NA

-e.

Suppression Pool Water Level - High NA f.

Manual Initiation NA 4.

AUTOMATIC DEPRESSURIZATIO_N_ SYSTEM a.

Reactor Vessel Low Water Level - Level 1 NA i

-b.

Drywell Pressure --High NA c.

ADS Timer NA

- _d.

Cure Spray Pump Cischarge Pressure - High

.NA e.

RHR LPCI Mode Pump Discharge Pressure - High NA

-f.

Reactor. Vessel Low Water Level - Level 3 NA

,g.

Manual Initiation NA h.

Drywell Pressure - High Bypass Timer NA

1.

Manual Inhibit NA 5.

LOSS OF POWER-a.

4.16 kV Emergency Bus Undervoltage (Loss e

of Voltage)

NA b.-

4.16 kV Emergency Bus Undervoltage (Degraded Voltage)

HA

)

  • These are permissive signals-only. They do not activate ECCS initiation.

M ECCS ACTUATION W 57t.MUEN MDC M L5 EUhuM ATf D W.oBA R6SPMf6 Tms Tscrwc..

3/4 3-29 AmendmentNo.AB,#,J,4h FEull - UNIT 2

  • J g-

,e-

+

,- - - - =

-- ~

r

4 e

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4 DiCLOSURE 3 - PART 2 PHOPOSED TECmlICAL SPECIFICATION RE71 SED PAGES

TABLE 3.3.1-2.

-REACTOR PROTECTION SYSTEM RESPONSE TIMES-

~ RESPONSE TIME.

A.

FUNCTIONAL UNIT (Seconds) 1.

Intermediate Range Monitors:

'~

a.

Neutron Flux - High NA

.E b.

Inoperative NA.

j G

2.

Average Power Range Monitor *:

m a.

Neutron Flux - High, Setdown NA b.

Flow Biased Simulated Thermal Power - High -

-6.i 1**

c.

Fixed Neutron Flux - High s 0.09 d.

Inoperative NA 3.

Re:*. tor Vessel Steam Dome Pressure - High s 0.55#

4.

Reactor Vessel Low Water Level - Level 3 s 1.05#

5.

Main Steam Line Isolation Valve - Closure s 0.06 6.

Main Steam'Line Radiation - High NA 7.

Drywell Pressure - High -

NA M

8.

Scram. Discharge-Volume Water Level - High a.

Float Switch NA

[

b.

Level Transmitter NA 9.

Turbine Stop Valve - Closure s 0.06 10.

Turbine Control Valve Fast Closure s 0.08***

11.

Reactor Mode' Switch Shutdown Position NA

12. Manual Scram NA y
13. Deleted
  • Neutron detectors are exerrpt from response time testing.

Response time shall be measured from the de'ec+ar 7utput or from the input of the first electronic component in the channel.

y

    • Including simulated thermal power time constant.

Rj

      • Measured from deenergization of K-37-relay-wSich inputs the turbine control valve closure signal i

to the RPS.

U

  1. ensor is eliminated from response time testing for the RPS circuits. Response time testing S

and conformance to the administrative limits for the remaining channel including trip unit and relay logic are required.

/

TABLE 3.3.2-3

-1SOLAT10N ACTUATION SYSTEM INSTRUMENTATION RESPONSE TIME TRIP FUNCTION-RESPONSE TIME (Seconds 1

-1,

."fluiARY CONTAINMENT L5D.LA_110J a.

Reactor Vessel-Low Water Level 1)

Level 3 NA 8

2)-

Level 2 NA

-3)

Level 1 s 1.0*##/NA b.

Drywell Pressure - High NA c.

Main Steam Line 1 )_-

Radiation - High(b)

NA###

2)

Pressure-- Low-NA-I 3)

' Flow - High s0.S*##/NA l

d.

Main = Steam Line Tunnel Temperature - High NA

-e.

Condenser Pressure - High NA f.

Turbine Bldg.-Area Temperature - High NA g.

Deleted.

NA h.

Manual Initiation 2.

REACTOR WATER CLEANUP SYSTEM ISOLATION a.

A Flow' -High NA b.

l; cat-Exchanger / Pump /High Energy Piping Area Temperature - High NA c.

Heat Exchanger / Pump / Phase Separator Area Ventilation Temperature AT High NA d.- -SLCS Initiation NA e.

Reactor Vessel Low Water Level - Level 2 NA l

f.~

~ Deleted--

g.

Manual Initiation NA 3.

. REACTOR CORE ISOLATION COOLING SYSTEM ISOLATION L

a.

RCIC Steam Line Flow - High NA-L b.

RCIC Steam Supply Pressure - Low NA c.

RCIC Turbine Exhaust Diaphragm Pressure - High NA

d.

RCIC Equipment Room Temperature - High NA e.

Manual Initiation NA-g l;-

l'

. FERMI - UNIT _2 3/4 3-18 Amendment-No. /J, AJ, r:

m e

h e.

- TABLE 3.3.2-3 (Continued)

I'iOLATION ACTUATION SYSTEM INSTRUMENTATION RESPONSE TIME TRIP FUNC_T.LQH RESPONSE TIME (Seconds)#

-4.

HIGH PRESSURE COOLANT INJECTION SYST[M ISOLATION a.

HPCI Steam Flow - High NA b.-

HPCI Steam Supply Pressure - Low NA l

c.

HPCI Turbine Exhaust Diaphragm Pressure --High NA d.

HPCI Equipment Room Temoerature - H3gh NA e.

Manual Initiation NA 5.

RHR SYSTEM SHUTDOWN C00LliiG MODE ISOLATION a.

Reactor Vessel Low Water Level - Level 3 NA b.

Reactor Vessel (Shutdown Cooling Cut-in Permissive Interlock) Pressure - High NA c.

Manual Initiation NA

'6.

SECONDARY CONIAINMENT ISOLATION a.

Reactor Vessei Low Water Level - Level 2 NA i

I b.

Drywell: Pressure - High -

Fuel Pool Yantilation Exhaust Radiation - High(D) NA NA c.

d.

Manual Inination.

No (a) Caleted

-(b) Radiatio _n detectors are exempt from response time _ testing.

Response time shall-be measured from detectnr output or the input of the first electronic component in the channel.

  • Isolation system instrumentation response time for MSIVs only.

No diesel

. gencrator delays assumed for MSIVs.

l

  1. solation' system instrumentation response time specified for the Trip I

function ~ actuating each valve group shall be added to isolation time shown in Table 3.6.3-I and 3.6.S.2-1 for valves in each valve group to obtain ISOLATION SYSTEM RESPONSE TIME for each valve.

.## Sensor is eliminated from response time testing for the MSIV actuatien logic circuits..-Response time testing and conformance to the administrative limits for the remaining channel including trip unit and relay logic 'are required.

      1. esponse time testing 'is eliminated for the radiation loops based on the R

-qualified Log Rad Monitors.

FERMI - UNIT 2 3/4 3-19 Amendment No M,

1

~

m u

v e

-~-

I c

IMLE 3.3.3-3 LMERGENCY C.QR LC00 LING SYSTEM RESPONSL TIMES RESFONSE TIME 1RLP FUNCT_LQii

.(Second.31 1.

RQBLSPRAY SYSTlM a.

Reactor Vessel low Water Level - Level 1 s 30#

l b.

Dryweli Pressure - High s 30#

c.

Reactor Steam Dome Pressure - Low NA*

d.

Manual Initiation NA 2.

1.0W PRESSURE COOLANT INJECTION MODE OF RHR SYST[d a.

Reactor Vessel Low Water Level - Level 1 s 55#

5 l

b.

Drywell Pressure - High s 55#

c.

Reactor Steam Dome Pressure Low NA*

i d.

Reactor Vessel low Water Level - Level 2 NA e.

Reactor Storm Dome Pressure - Low NA i

l f.

Riser Differentiul Pressure - Hir NA

)

g.

Recirculation Pump Differential Pressure -

NA i

o High h.

Manual Initiation NA 3.

HIGH PRESSURE COOLANT INJECTION SYSTEM l

a.

Reactor Vessel Low Water Level - Level 2 s 30#

j b.

Drywell Pressure - High NA c.

Condensate Storage Tank Level - Low NA d.

Reactor Vessel Water Level - High, Level 8 NA e.

Suppression Pool Water Level - High NA f.

Manual Initiation NA i

4.

.A.UTOMATIC DEPRELSURIZATION SYSTEM a.

Reactor Vessel Low Water Level - Level 1 NA b.

Drywell Prescure - High NA c.

ADS limer NA d.

Cere Spray Pump Discharge Pressure - High NA i

e.

RHR LPCI Mode Pump Discharge Pressure - High NA f.

Reactor Vessel Low Water Level - Level 3 NA g.

Manual Initiation NA h.

Drywell Pressure - High Bypass Timer NA 1.

Manual Inhibit NA S.

LOSS OF PORE _E a.

4.16 kV Emergency Bus Undervoltage (Loss i

of Voltage)

NA l

b.

4.16 kV Emergency Bus Undervoltage l

(Degraded Voltage)

NA l

Tihese are permissive signals only.

They do not activate ECCS initiation.

  1. ECCS actuation instrumentation is eliminated from response time testing.

l FERMI - UNIT 2 3/4 3-29 Amendment No. JE, /E, 7f, J

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