ML17158B558
| ML17158B558 | |
| Person / Time | |
|---|---|
| Site: | Susquehanna  |
| Issue date: | 03/20/1996 |
| From: | PENNSYLVANIA POWER & LIGHT CO. |
| To: | |
| Shared Package | |
| ML17158B557 | List: |
| References | |
| NUDOCS 9603250113 | |
| Download: ML17158B558 (13) | |
Text
I/t DCmx 2!X Cz TIIIP FUNCTION
~SWIM OPHlASLE CHANNELS PE)I TIISs SYSTBl APPLICASLE OPBIATIONAL CONDll)ON8 CORE SPRAY SYSTEM a.
Reactor Vessel Water Level - Low Low Low, Level I 2ls) 1, 2. 3. 4
, 6 TABLE3.3.3-1 EMERGENCY CORE COOLING SYSTEM ACTUATIONINSTRUMENTATION ACTION 30 Ca)
O D
hlD b.
DryweN Presswe - High c.
Reactor Vessel Steam Dome Presawe - Low IP<<m)ss)ve) d.
Manual )nit)at)on 2.
LOW PRESSURE COOLANT INJECTION MODE OF RHR SYSTEM a.
Reactor Vassal Water Level - Low Low Low. Level I b.
Drywel Pressure - High c.
Ileacsor Vessel Stean Dome Pressure - Low IP<<missive)
- 1) System lnldadon
- 2) Reckcutstion Discharge Valve Closure d.
Manual initiation 2ls) 2ls) 1/subsystem 2lsl 2ls) 2(sl 2ls) 1/subsystem 1,2,3 I,2,3,4,6
- 1. 2. 3, 4, 6
- 1. 2, 3 IL2, 3 4,6 1~2, 3 4.6 1, 2. 3, 4, 6 30 31 32 33 30 30 31 32 31 32 33 3
R O
9'603250ii3 960320 PDR ADGCK 05000387 3.
HIGH PRESSURE COOLANT INJECTION SYSTEMS a.
Reactor V4$44) Wat4r Lev4) - Low Low, L4val 2 b.
Dryweg Presswe - High c.
Condensate Storage Tank Level - Low
~ ~
S 4
I 4'tef v4) lg Reactor Vessel Water Level-High, Level 8 ts P.
Manual Initiation 2lsl 2lsl 2ls)(b) 2(c) 1/system
- 1. 2, 3 1,2,3
- 1. 2, 3 1,2,3 1,2,3 30 30 34 31 33 I
I I
j 0
O 0
O I
TABLE 3.3.3-1 {Continued)
EMERGENCY CORE COOUNQ SYSTEM ACTUATION INSTRUMENTATION C
CD (a)
A channel may be placed In an inoperable status for up to 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> for required surveillance without placing the trip system in the tripped condition provided at least one OPERABLE channel ln the same trip system Is monitoring that parameter.
(b)
One trip system.
Provides,s)gnal to HPCI pump suction valves only.
(c)
Two out of two logic.
(d)
Either 4d or 4e must be satisfied.
The ACTION ls required to be taken only If neither ls satisfied. A channel ls not OPERABLE un)ess its associated pump la OPERABLE par Specification 3.6.1.
(e)
Within an AOS Trip System there are two logic subsystems, each of which contains an overall pump permissive.
At least one channel associated with each of these overall pump permlsslvas shall be OPERABLE.
(I)
A channel may be placed In an Inoperable status for up to 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> for required surveillance testing provided that all channels in the other trip system are OPERABLE.
When the system Ia required to ba OPERABLE per Specification 3.6.2 Not required to ba OPERABLE when reactor steam dome pressure Is less than or equal to 160 psig.
Required when FSF equipment is required to be OPERABLE.
foot required to be OPERABLE when reactor steam dome pressure is lass than or equal to 100 pslg.
Required to be OPERABLE only when Diesel Generator E ls either aligned to tha Class 1E system or not aligned to the Class 1E system but operating on the Test Facility.
The edlo tlo nsfer f Hp I pu suotl n fr m t oondffttsettfrstor peglhkyt'su@iree on oilln +hi hgsp~psjsanyaof water la el o rs o wh HP Injec n v ve I open+
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t."
h ENERGENCY CORE COOLING SYSIEN hCIORIION INSIRNENIRIION SEIPOINIS TRIP fNCT ION CORE SPRAY SYSTN a.
Reactor Vessel itater Level - Los Lov Lo~, Level 1
b.
Qryrell tressure - High c.
Reactor Vessel Steam Oaae Pressure
- Lm d.
. Hanual Initiation 2.
LM PRESSURE COOLNT INECTION ISOE OF RHR SYSTEM a.
Reactor Vessel Water level - Les Lm Les, level 1
b.
Orle) I Pressure
- High c.
Reactor Vessel Steno Ooee Pressure
- Lm TRIP SETPOINT
>-129 inches~
c 1.72 psig
> 436 psig, decreasing N
>-129 inches c 1.72 psig ALLOMABLE VALUE
>-136 inches
< 1.88 psig
> 416 psig, decreasing N
>"136 inches' 1.88 psig GOO I)
Systea Initiation 2)
Recirculation Qischarge Valve Closure 4.
Nanual Initiation 3.
HIGH PRESSNE COOUWT INECTION SYSTN
>436 psig, decreasing
>416 psig, decreasing
>236 psig, decreasing
>216 psig, decreasing O
a.
Neactor Vessel itater level " let Lac, level 2 b.
Orwell tressure - High c.
Condensate Storage Tank Love) - les d
React ater level - Hi level 8 P. ~Ps
+Poo Ms r jsrso -Plgj' n
at on
>-38 inches~
c 1.72 psig
> 36.0 inches above tank bottos c 54 inches fight hpc f N
> -45 inches c 1.88 psfg
> 36 g inches above tank bottw-c 55.5 inches 2g fPet NA 00 O crs CO 0 O
O 5
I
TNLE 1.3.3. l-I ENERGENCY CORE COOLING SYSTN ACTUATION INSTRUNENTAIIOH SURVEILLANCE RE UIRENENTS IRIP fUNCTION i.
CORE SPRAY SYSTEN CHANNEL OPF RATIONAL CHANNEL FUHCT IONAL CHANNEL CONDIIIONS FOR WHICH I EN YEW llBRIil II RUEI h
E RFtVIREII a.
b.
C.
4.
Reactor Vessel Mater level-Lo~ Los Low, level 1
Orwell Pressure
- High Reactor Vessel Steam Oowe Pressure - Low Hanual Initiation R
Q Q
1, 2, 3, h>>, 5>>
1, 2, 3, 1>>, 5" 1, 2, 3, 1", 5>>
2.
LN PRESSURE COOLANT INECTIOH %DE OF RHR SYSTEH a.
C.
3.
HIGH a.
b.
C.
Reactor Vessel Mater level-Lm Lm Lm, level 1
S Orwell Pressure
- High NA Reactor Vessel Steam Oowe Pressure - Lm Ij System Initiation N
2)
Recirculation Oischarge NA Valve Closure Hanual Initiation N
PRESSURE COOLANT INJECTION SYSTN Reactor Vessel Mater level-Low Los, level 2 S
O~ell Pressure - High N
Condensate Storage Tank level-N SWgtresgie Pal >>et Levee g>>
ac or Vessel Water i.evel-lligl>, Levei 8
>>A Hanuai Initiation N ~
R Q
gag l Q
NA 1, 2, 3, 1", 5>>
1, 2, 3 1, 2, 3, 1*, 5" 1, 2, 3, 1>>,
5>>
3 1>>
5>>
1, 2, 3
1,2,3 1, 2,.3 I, 2, 3
I, 2, 3
ENCLOSURE C TOPLAM28 Page 5 of )0 SU VEI LAN RE I
2.
For the HPCI system, verifying that the system develops a flow of at least 6000 gpm against a test line pressure of greater than or equal to 246 psig when steam is being supplied to the turbine at 150 k 15 psig.
3.
Perform)ng a CHANNELCAUBRATIOMofthe CSS header 4P instrumentation and verifying the setpoint to be c 1 paid.
- 4. Verifying that the suction for the HPCI system is automaticeHg.
from nd o
~ tank to the su p 'i<<
an a con ensate storage tank water lev.- Iow sign 5.
Performing a CHANNEL'AUBRATIONof the condensate transfer pump discharge Iow pressure alarm instrumentation and verifying the low pressure alarm setpoint to be a 113 psig.
d.
For the ADS:
- 1. At least once per 31 days, performing a CHANNELFUNCTIONALTEST ofthe accumulator backup compressed gas system low pressure alarm system
- 2. At least once per 18 months:.
a)
Performing a system functional test which includes simulated automatic actuation of the system throughout its emergency operating sequence.
but exc)uding actual valve actuation.
b)
Manually opening each ADS valve when the reactor steam dome pressure Is greater than or equa) to 100 pslg and observing that either:
1)
The control valve or bypass valve position responds accordingly, or 2)
There is a corresponding change in the measured steam flow.
,c)
Perform)ng a CHANNEL CAUBRATION of the accumulator backup compressed gas system low pressure alarm systems and verifying air alarm setpolnt of 2070 N 36 psig on decreasing pressure.
- e. At least every 18 months the following shall be accomplished by any series of
~
sequent)a).
over)app)ng or total channel steps such that the ent)re channel ia tested:
The provisions of Specification 4.0A are nat applicable pravidad the surveillance.-
is performed w)thin 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 to perform the test.
ADS solenoid energhat)on sha)I be used altemst)ng between ADS Division 1 and ADS Division 2.
SUSQUEHANNA - UNIT 1 3/4 6-5 Amendment No.
130
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TABLE 3.3.3-1 (Continued)
EMERGENCY CORE COOLING SYSTEM ACTUATIONINSTRUMENTATION
"]1 j,'
I
~
'I
> Lee, Level 1
O'neil Pressure
" High Reactor Vessel Steaa Ooae Pressure - Los Hanual Initiation
>-129 inches"
< 1.72 psig
> 136 psig, decreasing HA
>-136 inches
< 1.88 psig
> ll6 psig, decreasing NA 2.
LOH PRESSURE COOLANT ILIECTION HODE OF RHR SYSTEH a.
Reactor Vessel Mater Level - Los Los Los, Level 1
Orpull Pressure
- High Reacler Vessel Steaa Dost Pressure
- Los l)
Systea Initiation 2)
Recirculation Discharge Valve Closure Nanual Initiation
>-129 inches"
< 1.72 psig
>-136 inches
< 1.88 psig
> 436 psig, decreasing
> 416 psig, decreasing
> 236 psig, decreasing
> 216 psig, decreasing HA NA 3.
HICIH PRESSURE COOLANT INECTION SYSTEH a.
h.
Reactor Vessel Mater Level - Lo~ Low, Level 2 Orwell Pressure
- High Condensate Storage Tank Level - Lee
> -38 inches"
< 1.72 psig
> 36.0 Inches above tank bottoa
> -45 inches
< 1.8$ psig
> 36.0 inches above tank bottoe d.
Reactor Vessel Mater Level
.- High, Level 8 a/.'anual In)tlat ion
< 5I inches
< 55.5 inches
'33 IF:
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P f
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I TABLE4.3.3.1-1 EMERGENCY CORE COOLINQ SYSTEM ACTUATIONINSTRUMENTATIONSURVEILLANCEREQUIREMENTS ',!;":l.-
~n f)el
'-" TRIP FUNCTION CHANNEL CHANNEL CHANNEL CHECK FUNCTIONAL CALIBRATION TEST OPEAAYIONAL CONDITIONS FOR';
.'HICH SURVEILLANCE" AEauiAEO.:: '::
2.
o.
Reactor Vessel Water Level - Low Low Low, Lovel 1 b.
Orywoll Pressure - High c.
Reactor Vessel Steam Domo Pressure
- Low d.
Manual Initiation
~.
~ Low Low Low, Level 1
b.
OryweN Pressure
- High c.
Reactor Vessel Steam Oome Pressure
- Low 1)
System Initiation 2l Recirculation Oischarge Valve Closure d.
Manual Initiation S
NA NA NA S
NA NA NA NA Q
a Q
R a
a a
a A
R a
a NA R
a a
a NA 1,2,3,4,',6.',2,3 1234>>
6'.2.3,4
',6>>
1, I.
,I:
1,2,3,4',6'.,
1,2,3 1,2,3,4',6',2,3,4',6>>
1,2,3,4',6'
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P
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~ 1 il
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11'.
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1, I
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1(.
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p 1
!I'
,t i" l.
I'.
a.
Aoactor Vessel Water Level - Low Low, Lovel 2 b.
OryweN Pressure
- High c.
Condensate Storage Tank Lovel - Low d.p'.
Aeactor Vessel Water Level - High, Level 8 eg Manual Initiation S
NA NA NA NA
~l Pe,s I1Il'j, a
a a
A
~
a a
1,2,3 1,2,3 1,2.3
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1,2,3 1,2,3 II Pl I
P
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C E
UIR ENCLOSURE C TO PLA4428 Page 10 of 10 2.
For the HPCI system, verifying that the system develops a flow of at least
~
6000 gpm against a test line pressure of greater than or equal to 246 psig when steam is being supplied to the turbine at 160 a 16 psig.
3.
Performing a CHANNELCAUBRATIONofthe CSS header hP Instrumentation and verifying the setpoint to be 6 1 paid.
4.
Verifying that the suction for the HPCI system is automatlcaily transferred from the condensate storage tank to the sup ression chamber eire~~
on a condensate storage tank water level - Iow signal.
5.
Performing a CHANNEL CAUBRATION of the condensate transfer pump discharge tow pressure alarm instrumentation and verifying the low pressure alarm setpoint to be > 113 psig.
- d. For the AOS:
1.
At least once per 31 days. performing -a CHANNEL FUNCTIONALTEST of the accumulator backup compressed gas system Iow pressure alarm syste~
2.
At least once per 18 months:
a) Performing a system functional test which includes simulated automatic actuation of the system throughout its emergency operating sequence, but excluding actual valve actuation.
b) Manually opening each ADS valve when the reactor steam dome pressure is greater than or equal to 100 psig and obsenring that either:
1)
The control valve or bypass valve position responds accordingly, or 2)
There is a corresponding change in the measured steam flow.
The provisions of Specification 4.0.4 are not applicable provided the surveillance 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 to perform the'test.
ADS solenoid energhetion shaN be used alternating between AOS Division 1 and AOS Dbrision 2.
For the startup foNowing the Third Refueling and Inspection Outage, this surveIIIance sheN read as foNows:
For the HPCI System, verifying that the system develops a flow of at least 4860 gpm against a teat line pressman of 600 psig when steam is being supplied to the turbine at 160 e ~.
SUSQUEHANNA - UNIT 2 3/4 5-5 Amendment No.
10~
'I