ML20106C545
| ML20106C545 | |
| Person / Time | |
|---|---|
| Site: | Perry  |
| Issue date: | 09/28/1992 |
| From: | CENTERIOR ENERGY |
| To: | |
| Shared Package | |
| ML20106C537 | List: |
| References | |
| NUDOCS 9210060218 | |
| Download: ML20106C545 (12) | |
Text
_ --_-___________ _____ __-_ _ - - ______ _
TABLE 2.2.1-1 REACTOR PROTECTION SYSTEM INSTRUMENTATION SETPOINTS
~
l 9
ALLOWABLE FUNCTIONAL UNIT TRIP SETPOINT VALUE5 5
1.
Intermediate Range Monitor N@p*a ]
Neutron Flux-High
< 120/125 divisions
< 122/125 divisions a.
P full scale of full scale Ig b.
Inoperative M
NA o
2.
Average Power Range Monitor:
f
- ora a.
Neutron Flux-High Setdown
< 15Y of RATED
< 20% of RATED
' 95 THERMAL POWER THERMAL POWER l
b.
Flow Biased Simulated Thermal Power-High c,y ora
- 1) Flow Biased
< 0.66 W+64%, with
< 0.66 W+67% with.
8o i maximum of i eaximum of
~D C)PJ
- 2) High Flow Clamped
< 111.0% of RATED
< 113.0% of RATED i"xtS THERMAL POWER THERMAL POWER O
c.
Neutron Flux-High
< 118.0% of RATED
< 120.0% of RATED THERMAL POWER THERMAL POWER d..
Inoperative WA NA 3.
Reactor Vessel Steam Dome Pressure - High i 1064.7 psig 5 1079.7 psig 4.
Reactor Vessel Water Level - Low, Level 3
> 177.7 inches above
> 177.1 inches above Iop of active fuel
- top of active fuel
- l 5.
Reactor Vessel Water Level-Figh, Level 8
< 219.5 inches above
< 220.1 inches above-Top of active fuel" Iop of active fuel
- i 1
6.
Main Steam Line Isolation Valve - Closure
-< 8% closed
< 12% closed v
V-V V
7.
Paf-Stc r Linc 9:dictfi- - ufsh Deleted
- 3.0 x ful' pcaer
< 3. 6 - fe!' pcuer l
N
@ Egr:and-chgrcund
/
~
8.
Drywell Pressure - High 1 1.68 psig 5 1.88 psig 7 g 3,.
xn'ER "See Bases Figure B 3/4 3-1.
-lC
?, 3 E
._ ~ 9 r
L
TABLE 3.3.1-1 A
REACTOR PROTECTION SYSTEM INSTRUMENTATION jg APPLICABLE MINIMUM OPERATIONAL OPERABLE CHANNELS E
FUNCTIONAL UNIT CONDITIONS PER TRIP SYSTEM (a)
ACTION Z
1.
~
a.
Neutron Flux - High 2
3 1
3 3
2 5(bj 3
3 b.
Inoperative 2
3 1
3, 4 3
2 5
3 3
2.
Average Power Range Monitor (c);
a.
Neutron Flux - High, Setdown 2
3 1
w 3
3 2
2 5(b) 3 3
Y b.
Flow Biased Simulated Thermal Power - High 1
3 4
c.
Neutron Flux - High 1
3 4
d.
Inoperative 1, 2 3
1 3
3 2
5 3
3 3.
Reactor Vessel Steam Dome Pressure - High 1, 2(d) 2 1
4.
Reactor Vessel Water Level - Low, Level 3 1, 2 2
1 5.
Reactor Vessel Water Level - High, Level 8 1(*)
2 4
6.
Main Steam Line Isolation Valve -
Closure
- )
234 4
4 4{j 7.
iaia Steam Line DadieHon -
Deleted V
N,
"?O W^
W
+
s 8.
_ Drywell Pressure
'High 1, 2 2
1
-- o_
n---m
PY-CEI/NRR-1439'L Page 3 of 11 TABLE 3.3.1-1 (Continued)
REACTOR PROTECTION SYSTEM INSTRUMENTATION ACTION ACTION 1 Be in at least HOT SHUIDDWN within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
ACTION 2 Verify all insertable control rods to be inserted in the core and lock the reactor mode switch in the Shutdown position within one hour.
ACTION 3 Suspend all operations involving CORE ALTERATIONS
- and insert all insertable control rods within one hour.
ACTION 4 Ce in at least STARTUP ithin 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
ACTION 5 Oc in STARTUP with the main stcas line i3cletica ;-lvc; cle:e4
.;ithin C hour:--cr in at lec,t-HOT S"UT00WN wkMn-12 hour',.
Deleted h
_s ACTION 6 Initiate a reduction in THERMAL POWER within 15 m nu
-and reduce turbine first stage pressure to less than the automatic bypass setpoint within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.
ACTIO' 7 Verify all insertable control rods to be inserted within one hour.
ACTION 8 Lock the reactor mode switch in the Shutdown position within one hour.
ACTION 9 Suspend all operations involving CORE ALTERATIONS *, and insert all insertable control rods and lock the reactor mode switch in l
the Shutdown position within one hour.
l l
- Except replacement of LPRM strings provided SRM instrumentation is OPERABLE per Specification 3.9.2.
PERRY - UNIT 1 3/4 3-4
TABLE 3.3.1-2
~
3 REACTOR PROTECTION SYSTEM RESPONSE TIMES T
~
RESPONSE TIME c3 FUNCTIONAL UNIT (Seconds) w 1.
~
a.
Neutron Flux - High NA b.
Inoperative NA 2.
Average Power Range Monitor *:
a.
Neutron Flux - High, Setdown NA b.
Flov Biased Simulated Thermal Power - High
< 0.09**
c.
Neutron Flux - High 7 0.09 d.
Inoperative RA 3.
Reactor Vessel Steam Dome Pressure - High
< 0.35 7
y 4.
Reactor Vessel Water Level - Low, Level 3
_ 1.05 5.
Reactor Vessel Water Level - High, level 8
< 1.05 i e
' ~h 3.igr[
'NA-8.
Dr 9.
Scram Discharge Volume Water Level - High NA 10.
Turbine Stop Valve - Closure
-< 0.06 11.
Turbine Control Valve Fast Closure, Valve Trip System Oil Pressure - Low
< 0.07#
12.
Reactor Mode Switch Shutdown Position RA
- 13. Manual Scram NA
- Neutron detectors are exempt from response time testing.
Response time shall be measured from the detector output or from the input of the first electronic component in the channel.
- Not including simulated thermal power time constant, 6 1 0.6 sec)nds.
- Measured from start of turbine control valve fast closure.
y>,
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%9
if C
,35
-x 2N Oo t*
A TABLE 4.3.1.1-1 l
m REACTOR PROTECTION SYSTEM INSTRUMENTATION SURVEILLANCE REQUIREM t
c CHANNEL OPERATIONAL CHANNEL FUNCTIONAL CHANNEL CONDITIONS IN WHICH
}
FUNCTIONAL UNIT CHECK TEST CAL:8 RATION (a)
SURVEILLANCE REQUIRED 1.
Neutron Flux - High S/U.S,(b)
S/U
,W R
a.
IC}
2 5
W R
3, 4, 5 b.
Inoperative NA W
NA 2.
Average Power Range Monitor:(f) 2,3,4,5 Neutron Flux - High, S/U.S,(b)
S/U a.
IC)
Setdown
,W SA 2
S W
SA b.
Flow Biased Simulated 3, 5 Thermal Power - High 5,0(h) y y(d)(e), gg(m),R I
II)
Neutron Flux - High 5
W W
c.
Id)
{
, SA 1
d.
Inoperative NA V
NA 1,2,3,5 3.
Reactor Vessel Steam Dome Pressure - High I9) 5 M
R 4.
1, 2(d) -
Low, level 3 I9)
S M
R 5.
1, 2 High, Level 8 I9) 5 M
R 6.
Main Steam Line Isolation 1
Valve - Clos p HA M
7 M:f-Ste r b r.e % distion - ~
R 1
Deleted D
A A
A 8.
Drywell Pressure - High S
M R
\\_
9.
Scram Discharge Volume Water 1, 2 Level - High 7 g y.
i;A a.
Lev-1 Transmitter S
M RI9)
,@O 1, 2, 5(k) gg b.
Float Switches NA M
R I)
_ "T 1, 2, S
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TABLE 3.3.2-1 Ag ISOLATION ACTUATION INSTRUMENTATION a
VALVE GROUPS MINIMUM APPLICABLE g
OPERATED BY OPERABLE CHANNELS OPERATIONAL 3
TRIP FUNCTION SIGNAL PER TRIP SYSTEM (a)
CONDITION ACTION
~
1.
PRIMARY CONTAINMENT ISOLATION a.
Low, Level 2 1,5,7,8 2
1, 2, 3 and #
20 b.
Drywell Pressure - High 1,2,5,8,9 ')(C) 2 1,2,3 20 c.
Containment and Drywell Purge Exhaust Plenum Radiation - High 8
2(9) 1, 2, 3 and
- 21 d.
Low, Level 1 2( )(c) 2 1, 2, 3 and #
20 e.
Manual Initiation 1,2,5,7,8,9 2(k) 1, 2, 3 and
- 22 y
2.
MAIN STEAM LINE ISOLATION U
a.
Low, Level 1 6
2 1,2,3 20 b.
-A Radiation - High 6(d)
I#)
I, 2 m 4M c.
Main Steam Line Pressure - Low 6
2 1
24 d.
Flow - High 6
2/line 1,2,3 23 e.
Condenser Vacuum - Low 6
2 1,
2**,
3*'
23 f.
Main Steam Line Tunnel
[hf.
Temperature - High 6
2 1,2,3 23 g.
Main Steam Line Tunnel
' E. S
{
A Temperature - High 6
2 1,2,3 23
[~ $
{
h.
Turbine Building Main Steam "EE Line Temperature High 6
2 1,2,3 23 2,o
.l.
Manual Initiation 6
2 1,2,3 22' M
r
PY-CEI/NRR-1439 L
^
TABLE 3.3.2-1 (Continued) j' p
ISOLATION ACTUATION INSTRUMENTATION ACTION In OPERATIONAL CONDITION 1, 2 or 3, be in at least HOT SHUTDOWN ACTION 20 within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in CCi.D SHUTDOWN within the next 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
In OPERATIONAL CONDITION #, suspend CORE ALTERATIONS and operations withj potential for draining the reactor vessel.
Close the affected system isolation valve (s) within one hour or:
ACTION 21 a.
In OPERATIONAL CONDITION 1, 2 or 3, be in at least HOT SHUTOOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLD SHUTDOWN within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, b.
In Operational Condition *, suspend CORE ALTERATIONS, handling of irradiated fuel in the primary containment and operations with a potential for draining the reactor vessel.
Restore the manual initiation function to OPERABLE status ACTION 22 within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> or:
a.
In OPERATIONAL CONDITION 1, 2, or 3, 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 in COLD SHUTDOWN within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
b.
In OPERATIONAL CONDITION *, suspend CORE ALTERATIONS, operations with a potential for draining the reactor vessel, and handling of irradiated fuel in the primary containment.
Be in at least STARTUP with the associated isolation valves ACTION 23 closed within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> or be in at least HOT SHUTOOWN within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLD SHUTIiOVN within the next 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
ACTION 24 Be in at least STARTUP within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />, ACTION 25 Verify SECONDARY CONTAINMENT INTEGRITY with the annulus exhaust gas treatment system operating within one hour.
ACTION 26 Restore the manual initiation function to OPERABLE status within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> or close the affected system isolation valves within I hour and declare the affected system inoperable.
ACTION 27 Close the affected system isolation valves within one hour and declare the affected system inoperable.
ACTION 28 Within one hour lock the affected system isolation valves closed, or verify, by remote indication, that the valve (s) is closed and electrically disarmed, or isolate the penetration (s) and declare the affected system inoperable.,
.y-ACTION 29 -
Close the associated isolation valves within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> or be in at least OY HOT SHUTDOWN within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
.A
_W When handling irradiated fuel in the primary containment and durin; CORE ALTERATIONS and operations with a potential for draining the reactor vessel.
When any turbine stop valve is greater than 90% open and/or the key locked Condenser Low Vacuum Bypass Switch is in the normal position.
During CORE ALTERATIONS and operations with a potential for draining the reactor vey el.
- M OPERATIONAL CONDITION I or 2 when the mechanical vacuum pump lines are not isolated.
~
sh PERRY - UNIT 1 3/4 3-15 Amenament No.M,42
PY-CEl/NRR-1439 L Xa Page C~ef i1
^
-TABLE 3.3.2-1 (Continued).
ISOLATION ACTUATION INSTRUMENTAT~0N 1
ACTION NOTES (Cor,tinued)
(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 con-dition provided at least one other OPERABLE channel in the same trip Jystem is monitoring that parameter.
(b)' Also actuates the standby subsystem of the annulus exhaust gas treatment system.
. (c) Also actuates the control room emergency filtration system in the recir-culation mode of operation. ~r (d) 1:0 tHp :nd i:01:te: the echen!::1 v: cur r- :-
.A s
+
(e) Closes only Rwcu system isolation valve (s) 1G33-F004 (SLCS Pump A) and 1G33-F001 (SLCS Pump B).
(f) Manual initiation isolates IE51-F064 and 1E51-F031 only and only following manual or automatic initiation of the RCIC system.
(g) Containment and Drywell Purge System inboard and outboard isolation valves each use a separate two out of two isolation logic.
(h) Requires RCIC system-steam supply pressure - low coincident with drywell pressure high to isolate valve 1E51-F077.
(i) For this signal, one trip system has two channels which close valves 1E51-F063.and-1E51-F076 while the other trip system has two channels which clcse valve 1E51-F064.
l (j)
_ k) There is only one (1) RCIC n.anual initiation channel for valve group 9.
(
_s - -
This Trip Function no longer isolates the Main Steam Lines. The only isolation is of the mechanical vacuum pump lines (valves IN62-F130A and t
B), using a single trip system consisting of two channels configured-a one-out-of-two logic.
x
-vx PERRY - UNIT 1 3/4-3-16
PY-CEI/NRR-1439 L Attachment Page 9 of II TABLE 3.3.2-3 ISOLATION SYSTEM INSTRUMENTATION RESPONSE TIME TRIP FUNCTION RESPONSE TIME (Seconds)#
1.
PRIMARY CONTAINMENT ISOLATION a.
Reactor Vessel Water Level - Low, level 2 NA b.
Drywell Pressure - High NA Containment and gell Purge Exhaust P'renum
< 16,)
c.
Radiation - High d.
Reactor Vessel Water Level - Low, Level 1 RA e.
Manual Initiation NA 2.
MAIN STEAM LINE ISOLATION Reactor Vessel Water Level - Lo%"iavel 1
< 1 0"/< 1 $"
N A a.
b.
Main Steam Line Radiation - Hig u, 1. 0,
c.
Main Steam Line Pressure - Low
< 1. 0 */< 10 8
d.
Main Steam Line Flow - High 7 0.5*/2 10(a),,
e.
Condenser Vacuum - Low NA f.
Main Steam Line lunnel Temperature - High NA g.
Main Steam Line Tunnel A Temperature - High NA h.
Turbine Building Main Steam Line Temperature - High NA i.
Manual Initiation NA 3.
SECONDARY CONTAINMENT ISOLATION a.
Reactor Vessel Water Level - Low, Level 2 NA b.
Drywell Pressure - High NA c.
Manual Initiation NA 4
REACTOR WATER CLEANUP SYSTEM ISOLATION l
a.
A Flow - High NA b.
A Flow Timer NA c.
Equipment Area Temperature - High NA d.
Equipment Area A Temperature - High NA i
e.
Reactor Vessel Water Level - Low, Level 2 NA f.
Main Steam Line Tunnel Ambient Temperature - High NA g.
Main Stea::: Line Tunnel A Temperature - High NA l
h.
SLCS Initiation NA i.
M6nual Initiation NA l
PERRY - UNIT 1 3/4 3-21
TABLE 4.3.2.1-1 h
ISOLATION ACTUATION INSTRUMENTATION SURVEILLANCE REQUIREMENTS n)
CHANNEL OPERATIONAL CHANNEL FUNCTIONAL CHANNEL CONDITIONS IN WHICH TRIP FUNCTION CHECK TEST CALIBRATION SURVEILLANCE REQUIRED c:jz
~
1.
PRIMARY CONTAINMENT ISOLATION a.
Rff 1, 2, 3 and #
Low, Level 2 5
M b.
Drywell Pressure - High 5
M R
1, 2, 3 c.
Containment and Drysell Purge Exhaust Plenum Radiation -
High 5
M R
1, 2, 3 and
- d.
R(b) 1, 2, 3 and #
Low, Level 1 5
M e.
Manual Initiation NA R
NA 1, 2, 3 and
- 2.
MAIN STEAM LINE ISOLATION a.
R(b) 1, 2, 3 g
Low, Level 1 5
M m
b.
Main Steam Line Radiation -
l m4 High 5
M P
1, 2 p- + +
w c.
Main Steam Line 'ressure -
R(b) y l
Low S
M Rf 1,2,3 d.
Main Steam Line flow - High S
M e.
Condenser Vacuum - Low 5
M R
1, 2**, 3**
f.
Main Steam Line Tunnel Temperature - High 5
M R
1, 2, 3 g.
Main Steam Line Tunnel A Temperature - High 5
M R
1, 2, 3 b.
Turbine Building Main Steam Line Temperature - High 5
M R
1, 2, 3 i.
Manual Initiation NA R
NA 1, 2, 3 2 R Ji SE5
_e5 2s 2, E E
-.,o.'.
C e
F g
s TABLE 4.3.2.1-1 (Continued)
~
y ISOLATION ACTUATION INSTRUMENTATION SURVEILLANCE REQUIREMENTS E
CHANNEL OPERATIONAL CHANNEL FUNCTIONAL.
CHANNEL CONDITIONS IN WHICH E
TRIP FUNCTION CHECK TEST CA!!BRATION SURVEItLANCE REQUIRED
-4 6.
RHR SYSTEM ISOLATION-a.
RHR Equipment Area Ambient Temperature - High S
H R
1, 2, 3 b.
-RHR Equipment Area a Temperature - High S
H R
1, 2, 3 c.
RHR/RCIC Steam Lina Flow - High 5
M R(b) 1,2,3 d.
Low, Level 3 5
H R(b) 1, 2, 3 Y
e.
Reactor Vessel (RHR Cut-in Permissive) Pressure - High S
M R(b) 1, 2, 3 f.
Drywell Pressure - High 5
H R(b) 1, 2, 3 g.
Manual Initiation NA R
NA 1,2,3
- When handling irradiated fuel in the primary containment and during CORE ALTERATIONS and operatione with a potential for draining the reactor vessel.
- When any turbine stop valve is greater than 90% open and/or the key locked bypass switch is in the normal position.
m>m
- 0uring CORE ALTERATION and operations with.a potential for draining the reactor vessel.
SE7 (a) Each train or logic channel shall be tested at least every other 31 days.
- $0 (b) Calibrate trip unit setpoint at least once per 31 days.
2EC W
hsf N
Y V
'kh g
NAN OPERATIONAL CONDITION I or 2 when the mechanical vacuum pump lines are tot isolated.
_y_..
A
_A A
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PY-CEI /NRR-14 39 L
' Attachment-3 Page 1 of' !
l a.
e 1
-t.
+
LIMITING SAFETY SYSTEM SETTINGS BASES REACTOR PROTECTION SYSTEM INSTRUMENTATION SETPOINTS (Continued) 4.
Reactor Vessel Water Level-Low The reactor vessel water level trip setpoint has beer used in transient analyses dealing with r.oolant inventory decrease.
The scram setting was chosen far enough below the normal operating level to avoid spurious trips but high enough above the fuel to assure that there is adequate protection for the fuct and pressure limits.
5.
Reactor Vessel Water Level-High A reactor scram from high reactor water level, approximately two feet above normal operating level, is intended to of fset the addition of reactivity ef fect associated with the introduction of a significant amount of relatively cold feedwater.
An excess of feedwater entering the vessel would be. detected by the level increase in a timely manner.
This scram feature is only effective when the reactor mode switch is in the Run position because at THERMAL POWER levels below 10% to 15% of RATED THERMAL POWER, the approximate range of power i
level for changing to the Run position, the safety margins are more than adequate without a reactor scram.
6.
Main Steam Line Isolation Valve-Closure The main steam line isolation valve closure trip was provided to limit the amount of fission product release for certain postulated cusnts.
The MSI 's closed automatically from measured parameters such as high steam flow, 'i;h a
te;r 'ine ragioLm;Q31ow reactor water level, high steam tunnel temperature an ow steam line pressure.
The MSIV's closure scram anticipates the pretsure-and flux transients which'could follow MSIV closure and-thereby protects reactor-vessel pressure and fuel thermal / hydraulic Safety Limits.
[
7.
M2?a Steam Line Radiatien-High..
Deleted The meia 5 team lins iedi6 tie 6 detector; er; prev 4ded te detect g re s s-Toiiuse ui ihe iucl cladding.
Whe6-thc'high radiat&cn is detected, a +"ip is initiated tc r; duce the 'ccatinued failur ;f fuci -ledding.
At th: :::: ti :
--the main ;tca; linc i elation valv;; crc cle: d te limit the rel;;;c of 'f ica preducts.
The trip : tting i:
igh cacugh ab;ve background radiation icvel 40- pre vc at-spuri cu trip; yct 1:w enough to preeptly detect gre;; failure:
i n the fuel c! adding.
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. PERRY - UNIT 1 B 2-8
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