ML20035G124
| ML20035G124 | |
| Person / Time | |
|---|---|
| Site: | Zion File:ZionSolutions icon.png |
| Issue date: | 04/22/1993 |
| From: | COMMONWEALTH EDISON CO. |
| To: | |
| Shared Package | |
| ML20035G118 | List: |
| References | |
| NUDOCS 9304260193 | |
| Download: ML20035G124 (20) | |
Text
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i ATTACHMENT D Marked up pages and typed pages for Proposed Technical Specification changes For License Amendment Request No. 93-01:
Change in Engineering Units Used to Measure The Intermediate Range High Flux Trip fron
" Amps" to "1. Rated Power" PAGES MODIFIED 7
14 30 31 32 37 131b l
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ZNLD/2563/15 9304260193 930422 PDR ADOCK 05000295 l
P PDR
~
ATTACHMENT D Marked Up Pages i
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ZNLD/2563/16
p SAFETY LIMIT LIMITING SAFETY SYSTEM SETTING 1.1 REACTOR CORE 2.1 REACTOR CORE Anolicability:
Apolicability:
Applies to the limiting combinations of thermal Applies to trip settings for instruments power, reactor coolarit system pressure, coolant monitoring reactor power and reactor coolant temperature and coolant flow when a reactor is pressure, temperature, flow and pressurizer level.
critical.
Qbjective:
Objective:
To maintain fuel cladding integrity.
To establish the trip set points for a reactor protection system such that the principal process variables do not exceed the safety limits rcquired for the applicable design limit DNBR.
4 Soecification:
Soecification:
1.
The combination of thermal power level, 1.
The limiting instrumentation set points for coolant pressure, and coolant temperature per reactor trip shall be set consistent with the
/.
unit shall not exceed the limits shown in following nominal trip setpoint values:
/
/
Figures 1.1-la and 1.1-lb for four-loop operation.
The safety limit is exceeded if A.
Startup protection f
the point defined by the combination of Reactor Coolant System average temperature 1.
High flux, power range (Iow set and thermal power level per unit is at any point): 1 25% of rated power.
time above the appropriate pressure line.
2.
High flux, intermediate range (high set ntT.furffhn~t equivalent tp125%
of power -A g
\\
N l
f'A Q 4
r A 4E M ts a f;w y % P t 'S 5 6 A7-ru s_. c_3.> <t swr h w A cryT vo y p p_ w,A m,E
{ 3[/o op. f-A TED Do wF E' v NPL Lh MtwOF_.T84Cd> bETEt_ web h t 9Gy Aygg _
Amendment Nos. in ""i M 7
i
.. -.-.....08..... _
Q.
Q-MTY I,IMIT LIMITING SAFETY SYSTEM SETTING O.
The power range high flux, low
- )
setpoint trip and the intermediate range h1 h flux, high setpoint 6
- trip % of rated power.shall be unblocked when g 10 D.
The source range high flux, high setpoint trip shall be unblocked whentheintermedgterangenuclear flux is{$ f T 10~. Emperea Q T
6 (O
/, ra.ted pouce 4
- c, Source ra,3e h.3L flot C,. e sk.il be v e ocKed
~
tae w the t.ntec liate. rawge muelcar how
-it ib 5 6 x.lO ilme e r e s umbt Ga. m m a Met e it. 5 deTecTo rs a re iu:cte lic i l
h wr.t>mEm NcG.
~-
1.
2.
3.
4 5.
6.
Is. Of Minismsa Minimum Operater Action e
R acter Trip Channel No. Of Channels Operahle Degree of If Colven 3 er 4 Deterlatten Per thlt Channels to Iris Channeln++e Redundanc y+++
fan Met Be Met Seteelnt:
1 Manwal Reactor Trly 2
1 1
9 Malatain Het htdowi'*.*
M.A.
2.
Power Range High Five 4
2 3
2 Maintain Het htdown".+
25% of Rated Neutron (Iow set point)-intertected F1va + t with P-10 3.
Power Range High Flus 4
2 3
2 Melntain Het Widemn".+
1091 of Rated Neutron Flen + +
(hlgh set point) 4 Power Range High F1wn Rate 4
2 3
2 Malatein Het Sheldown".+
51 of Rated Newtron Flus /2 sec. + +
5.
Megative Pe=er Range F1ws 4
2 3
2 Maintain Het h tdown**.+
f Rated Neutron F1ws/2 sec. + +
R:te Vlany 5
6)* Source Range Newtron Flun-2 1
1 9
Melntain Het htdown"*.+
19 g,,, g, f,,,, 4 +
Interlocked with P-19 and P-6 (or C50 if that conditten
'"I'
'I g
y J[4 47[tatermediateRangeNewtron 2
1 1
8 Halatain Het h tdown'.*
25% of Rated Meutron Flvs-Interlocked with P-10 Flus + +
- 8. Overteeperature AT. d Teers 4
2 3
2 Malatain Het h ide d *.+
ActualAT1PrograsuM
/
~'
//
i Setpoint t e
/
9.
Overpower AT. 4 1eeps 4
2 3
2 Heintain Het Shutdown".+
Actual AT 1 Programmed p
Setreint + +
j y
/
Melntain Het Shutdown ** +
1825 psig " ~
- 19. Presswelter Low Pressure-4 2
3 2
j laterlocked with P-7
/
i 11. Pressurtner High Pressure 4
2 3
2 Malatala Het Shutdown **
- 2385 Ps t g + /
- 12. Pressortier high Level -
3 2
2 1
Maintain Het htdown".+
921 of span + *
'(
- laterlocked with P-7 M
INS 6RT 3 :>
TABLE 3.1 1 Reacter Protection System - Limiting Operation Conditlens and Setpoints 30 Amendment Hes. G a..d 120 '
1.
'2.
3.
d.
5.
6.
No. Of Hinlaus Hinlaue Operator Action Reactor Trip Channe1 No. Of Channels Operable Degree of If Celeien 3 or 4 Dancriation Par Unit Channels Te_Iria Channeln++e Redundancy +e+
Can Not Be Met Satpalat
[
13a Low Primary Coelant flow -
Interlocked with
- a. P-7 3 per 1oop 2 per loop 2 per loop 1
Melntain Het htdown".+
901 of 99,300 spe
/
/
i in 2 loops (sintense measured Il flow)++
/
- b. P-8 3 per loop 2 per loop 2 per loop 1
Maintain Het htdown".+
in 1 loop e+13b.
Low Primary Coolant Flow -
\\
intertecked with
- a. P-7 3 per loop 2 per leep 2 per leep 1
Melntain Het htdown".+
901 of nominal span WWW In 2 loops
- b. P-8 3 per loop 2 per leep 2 per loop i
Heintain Het Shetdown",+
in 1 loop 14 RCP Bus Undervoltage -
1 per bus 2
3 2
Maintain Het htdown".+
75% of neelnal interlocked with P-7 voltage ++
)
15.
RCP Bus Underfreqwency -
1 per bus 2
3 2
Melntain Het htdown",+
57.0 Ma++
Interlocked with P-7 and P-8 16.
RCP Breaker Trip -
Interlocked with; a.
P-7. 4 loops 4 breakers 2
3 2
Maintain Het htdown".+
N.A.
/ :
b.
P-8, 4 loops 4 breaks,a 1
3 2
Maintain Het Sheldown",+
N.A.
/
. 17a.
Low Steam Generator Level 2 per loop 1 per loop 1
0 Maintain Het $hetdown".+
251 of narrow in coincidence with feed range lastrument
/
,p*
flow - steam flow mismatch 2 per loop 1 per loop 1
0 Heintain Het Shutdown **,+
span and elsmatch of 601 of 3.495 m 10' Ibs/hr (neelnel 1001,
/
steam flow rate).++
~
/
r iib."' tow steam sen.rator t.
i 2 per ioop i per ice, i
0 H intain Het sh.edown",+
25% of crew range in coincidence with feed instrumentspa e
flow - steam flow misantch 2 per loop 1 per loop 1
0 Maintain Het Shutdown",+
and 0.7 x 10 lbe/hr alsmetch.dOF Applicable to Unit 1.
Appilcab?e to Unit 2 at startup from refweling outage 221t12.
e o$
Not applicable to Unit 1.
Applicable to Unit 2 untl1 startup free refwe11pg outage Z21t12'..
TABLE 3.1-1 (Continued)
Reactor Protectlen System - Llel#W ysration Condittens and Setpointsd jg*
f AmrAi 31 l,.-: ut ",. A S W W
, ~ -. ~ ~ - - - - - -.. -. - - - - - - - - -. ~ -
- - - - - - - +
. ~ - -
~.. ~
~- -~
W Q
.~
FElul111L L SETPOINT X
P-4 10*I' amps" uptu. GAtitu tiEt Etc s Terne.ro p,5 ARE tOLTALLGD P-7 le Rated Neutron flew and Pressere gj g g, ;-
Etelvslent to 101 of Rated Turbine Leed P-8 281 et Rated Peuer 4 loops) for Unit I at startup free refueling estage ZlRIZ and Unit 2 at startop free refueling estage 22Rl2.**
~
}
(601 et Rated Power 14 loops) for Unit 2 entl1 startup f rom refuell_ng outage 22R12.888#
/
P-It 10E of Rated Neutron Flen "
9 If minteen conditions are not met within 24 heers. the unit shall be in the Cold Shotdeun conditlen within an additlenal 24 heers.
e S*tfeln%s_are_i est.abilshed tolerances _for lastrument channel and setpelat errors as specifled Inh *Cbannel A wescles. Overal[
M
++
/ Channel Accuracles and Setp3 Int Tolerances for W IIES Process I and C Reetter Protectlen and Centrol Systeme* Aegest 30, 1971,
LCtW452 for_ thlt 2 until startup from refueling estage 22R12 and as specified in[*2tw NSSS Setpoint Evelettw. protutta Syste f
Channels.' Eagle 21 Versten". Revision 1. Si1TgMfor Unit I at startup from rersellag estiiis ZlR12 and Unit 2 at startup)7 f
(from refueling outage Z2R12J The lastruments shall not be set to enceed a Lletting Safety System Setting.
For channel test, calibretten er maintenance, the minteen number of SPERAstt cleannels any be reduced by one but to not less than one,
+++
For Automatic and W minlaus degree of redundancy may be reduced by one bet to not less than more, for a seuleem of two heers.
Reacter Trip Logic and Reacter felp Breakers, the alleuable outage time is a manlaem of eight beers, m en block conditions entst, molntain normel operetten.
i
'penintain Het Shetde=c' means malatain er proceed to Met Shetdeun within four heers if the enocceptable condition arises during power operetten.
L Vert fy shutdeun omrgin lamediately and comply with Section 3.2.1.A.g.
Men 61ected conditions esist, sointain norus1 sporetten.
l During 9eedes 3. 4 or 5 and with the Reacter Trip System breakers closed and the Centrol Red Drive Systes capable of red withdreuel, O
f the following app 16est With the nauher of SPERMLE channels one less then the Minless gPERABLE Channels regetroesnt, resters the inoperable channel to SPERASLE states within 48 heers er open the Reetter trip brookers within the ment hour.
1 sw sering eedes 1 er 2 with one of the diverse trip feeteres (underveltage er Shent irly Attachesnt) leaperable, restore It to SPUIABLE p
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states within ed hours e-declare the breeter Insperable and meintain er proceed to Met Setdeun withle foer heers if the I
enocceptable conditlen arises during peuer operetten. The breaker skall not be bypassed chile one of the dheroe tyly featores is l
Insperable except for the ties required for perfereing salatenance and testing to restore the breater to WERMLE states.
Setpelats are a established tolerances for lastrument channel and setpelat errors as specified in 'Chennel Accuracles. Overall
/
sur Channel Acceracles and Setreint Telerances for W IEES Process I and C Reacter Protectlen and Centret Systeme* Augest 30, 1971 -
f j
CtW 652. The Instruments shall not be set to enceed a tietting Safety System Setting.
,l
\\
TABLE 3.I-1 (Continued) l i
./
b Reacter Protectlen System - tietting Operetten Condittens and Setpelats e
32 Amendment Ites. I O
insert,1 on ) qe 32:
10 t-
@ r "" af ter Gamma Metrics detectors are installed Insert 2 on Page 32:
'"' Setpoints are d-established tolerances for instrument channe, and set]oint errors as specified in " Zion NSSS Setpoint Evaluation Protecti System Caannels.
Eagle 21 Version. Non-Westinghouse Channels. Revision 0. March 993" The instruments shall not be set to exceed a Limiting Safety System Setting.
1 O
e O
e
=
Rain:
3.1 During a unit operation, the complete intentionally placed in a tripped mode since the test instruir.entation system will normally be in signal is superimposed on the normal detector signal service for that unit.
Reactor safety is to test at power.
Testing of the NIS power range provided by the Reactor Protection System, which channel requires:
(a) defeating the AT protection automatically initiates appropriate action to CH N L SET that is being fed from the NIS channel prevent exceeding established limits.
Safety is and (b) defeating the power mismatch section of Tavg not compromised, however, by continutng operation control channels when the appropriate NIS channel is with certain instrumentation channels out of being tested.
However, the rate trips on the service since provisions were made for this in remaining HIS channels still provide the dropped-rod the plant design.
This C ;cification outlines protection.
Testing does not trip the system unless limiting conditions for operation necessary to a trip condition exists in a concurrent channel.
(2) preserve the effectiveness of the Reactor Control and Protection System when any one or more of the channels is out of service.(1)
(1)
FSAR Section 7.2.1 The reactor protection system setpoints specified (2) FSAR Section 7.2.2 in Table 3.1-1 are the nominal values at which
/
the reactor trips are set.
The setpoint for a
/
reactor trip system or interlock function is considered to be set consistent with the nominal value when the "as measured" setpoint is within 16 F>rW MGTO'MAWEb N TNb
/
/
the band (established tolerance) allowed for g
gpg p__g, ggge gggg calibration accuracy. (
A R e i b rec N_ To v a r E_srceu wp_c.
Almost all channels are supplied with sufficient
% t e_ D A N u :4 Fo >_ t-s E r yrr_pmeA gg r
redundancy to provide the capability for channel g gq_
gg,p p-
- 4,-
p-calibration and test at power; the exceptions are S t 5UG W6 f5DE- ' C2 M CAL Gw c_E rnE backup channels such as reactor coolant pump breakers.
The removal of one trip channel on p4 g g reh-u F W'mW V S ES T H2F_
process control equipment is accomplished by placing that channel blstable in a tripped mode; MmE INSTA^3"^FNT'C4ANNF_tA (WD e.g., a three-out-of-four system becomes a DFJ Mo% MM I NTFEAFA W F
two-out-of-three cirevit.
The nuclear instrumentation system channels are not R P-N G,E_ tJ E A N FLir)'A G ANNE.Ls. A s C
E.-5.3TA 6*>LiS H 'b To L ERA AR5.6>
I
$ o.,- u TM pre -n+E_
t NTE PEEf31 AT6 RAMGE rdEuTRod 0~L UV-d H A N Nfd t, r\\PPLy FbEL T af_ P-L i N M P h a" G~U M c % o fd.
Amendment Nos.'l? m W 37
o o..
o..
If minimum conditions are not met within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, the unit shall be in the COLD SHUTDOMM condition within an
+
additional 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
y fChannel
.a_SetpointsareiestablishedtolerancesforinstrumentchannelandsetpointerrorsasskcifiedinReactor Protection and
{Accuracles,Dvera11'ChannelAccuraclesandSetpoinFf5TerancesforMNESProcessIand1971 - CEM-2652 for U f
Control Systems" August 30 Eagle 21 Versl6n"7 Revliton 1, April T992,qorj %
knOlignMSSSsetpointEval_uation,ProtectionSystemChannelsitMt startup from refueling out i
The Instruments shall not be s'et t6 eiiteed TLimiting Safety' System Setting.
~~
' ~ ~ ~ ~ ~ -
This channel may be placed in the bypass mode during periods of active testing during safeguards equipment e++
testing as specified in Section 4.4.2.
Setpoints are i estab11shed tolerances for Instrument channel and setpoint errors as specified in " Channel Accuracles, Overall Channel Accuracles and Setpoint Tolerances for R MES Process I and-C Reactor Protection and Control Systems" August 30,1971-CEHpS2. The Instruments shall not be set to exceed a Limiting $afety System f
Setting.
O Requires simultaneous actuation of two switches,
' Maintain Hot Shutdown' means maintain or be in NOT SMUTDONN within four hours if the unacceptab e condition l
A**
j arises during power operation.
3 i
i ENGINEERED SAFEGUARDS ACTUATION SYSTEM - LIMITING CONDITIONS FOR OPERATION AND SETPOINTS (Footnotes to Table)
TABLE 3.4-1 (Continued)
Amendment Nos. 439-and-128 131b
ATTACHMENT D Typed Pages l
ZNLD/2563/17
_ _ = - -
l SAFETY LIMIT LIMITING SAFETY SYSTEM SETTING l
l 1.1 REACTOR COBE 2.1 REACTOR CORE opplicability:
App]habili ty:
Applies to the 11miting combinations of thermal Applies to trip settings for instruments power, reactor coolant system pressure, coolant monitoring reactor power and reactor coolant temperature and coolant flow when a reactor is pressure, temperature, flow and pressurizer level.
critical.
ohlertin:
Objective:
To maintain fuel cladding integrity.
To establish the trip set points for a reactor protection system such that the principal process variables do not exceed the safety limits required l
for the applicable design limit DNBR.
Spe_cif1ca_ tion:
Specification:
1.
The combination of thermal power level, 1.
The limiting instrumentation set points for coolant pressure, and coolant temperature per reactor trip shall be set consistent with the unit shall not exceed the limits shown in following nominal trip setpoint values:
}
Figures 1.1-la and 1.1-1b for four-loop operation.
The safety limit is exceeded if A.
Startup protection _
j the point defined by the combination of r
Reactor Coolant System average temperature 1.
High flux, power range (low set and thermal power level per unit is at any point): 1 257. of. rated power.
l time above the appropriate pressure line.
2.
High flux, intermediate range (high j
set point):
1 25% of rated power.*
i I
Intermediate range high flux trip is set at the current equivalent to 1 25% of rated power until Gamma Metrics j
detectors are installed.
1 l
i i
1 ZOSR-295 7
Amendment Nos.
i
SAFETY LIMIT LIMITING SAFETY SYSTEM SETTING C.
The power range high flux, low setpoint trip and the Intermediate range high flux, high setpoint trip shall be unblocked when power is 1 10% of rated power.
D.
The source range high flux, high setpoint trip shall be unblocked when the intermediate range nuclear flux is 1 10-'% rated power.
- Source range high flux trip shall be unblocked when the intermediate range nuclear flux is 1 5 x 10-11 amperes until Gamma Metrics detectors are installed.
ZOSR-295 14 Amendment Nos.
1.
2.
3.
4.
5.
6.
No. Of Minimum Minimum Operator Action Reactor Trip Channel No. Of Channels Operable Degree of If Column 3 or 4 DJsi.r_iption Per Unit Channeh To Trio C_h.Annel s +++ Rgdyndancy+++ Can_NJi Bg_ Mal ___
icipoint l
r n
- 1. Manual Reactor Trip 2
1 1
0 Maintain Hot Shutdown",+
N.A.
- 2. Power Range High Flux 4
2 3
2 Maintain Hot Shutdown **,+
25% of Rated Neutron l
(low set point)-interlocked Flux ++
with P-10
- 3. Power Range High Flux 4
2 3
2 Maintain Hot Shutdown",+
109% of Rated l
(high set point)
Neutron Flux ++
- 4. Power Range High Flux Rate 4
2 3
2 Maintain Hot Shutdown **.+
5% of Rated Neutron Flux /2 sec. ++
l
- 5. Negative Power Range Flux 4
2 3
2 Maintain Hot Shutdown".+
-5% of Rated Neutron Rate Flux /2 sec. ++
5 j
v6a. Source Range Neutron Flux-2 1
1 0
Maintain Hot Shutdown"*,+
10 counts /sec. ++
Interlocked with P-10 and P-6 (or CSD if that condition exists) 5 vv6b. Source Range Neutron Flux-2 1
1 0
Maintain Hot Shutdown ***,+
10 counts /sec. ####
Interlocked with P-10 and P-6 (or CSD if that condition exists) v7a. Intermediate Range Neutron 2
1 1
0 Maintain Hot Shutdown *,+
25% of Rated Neutron Flux-Interlocked with P-10 Flux ++
vv7b. Intermediate Range Neutron 2
1 1
0 Maintain Hot Shutdown *,+
25% of Rated Flux-Interlocked with P-10 Power ####
v Applicable until Gamma Metrics Detectors are installed.
vv Not applicable until Gamma Metrics Detectors are installed.
e TABLE 3.1-1 Reactor Protection System - Limiting Operation Conditions and Setpoints ZOSR-295 30 Amendment Nos.
4 e
INSERT 1 ON PAGE 30 W 66. Source Range Neutron Flux-2 1
1 0
Melntain Het Shutdown ".+
10' counts /sec. dWWW Interlocked with P-10 and P-4 (or C50 if that conditten eul[ts)
INSERT 2 ON PAGE 30 W 7b. Intermediate Range Neutron 2
1 1
0 Maintain Hot Shutdown'.+
25% of Rated Flux-Interlocked with P-10 Power AWWW INSERT 3 ON PAGE 30 7 Appitcable until r-Metrics Detectors are installed.
gy Not appitcable untti Gasuna Metrics Detectors are Installed.
4 o
f o
4 t
se 4
.._,-,,-.e-m
=--
1.
2.
3.
4 5.
6.
No. Of Minimum Mlnloom Operator Action Reactor Trip Channel No. Of Channels Operable Degree of If Column 3 or 4
$gipqint l
Qgiglgign Per Unit Channals To Trio channels w+
Redundancy +++ Can Not Be Het
- 8. Overtemperature AT 4 loops 4
2 3
2 Maintain Hot Shutdown" 4 Actual af 1 Programmed Setpoint ++
- 9. Overpower AT. 4 loops 4
2 3
2 Maintain Hot Shutdown".+
Actual AT 1 Progranswd Setpoint u
- 10. Pressurizer Low Pressure-4 2
3 2
Maintain Hot Shutdown".+
1825 psig ++
interloc.ed with P-7
- 11. Pressurizer High Pressure 4
2 3
2 Halntain Hot Shutdown".+
2385 psig ++
4 i
- 12. Pressuriser High Level -
3 2
2 1
Maintain Hot Shutdown".+
927. of span
- Interlocked with P-7
- 13. Low Primary Coolant Flow -
l Interlocked with
- a. P-7 3 per loop 2 per loop 2 per loop 1
Maintain Hot Shutdown **.+
90% of 89.300 gpm in 2 loops (einleum measured flow)w
- b. P-8 3 per loop 2 per loop 2 per loop 1
Maintain Hot Shutdown **,+
j in 1 loop I
- 14. RCP Bus Undervoltage -
1 per bus 2
3 2
Halntain Hot Shutdown".+
75% of nominal Interlocked with P-7 voltagen i
- 15. RCP Bus Underfrequency -
1 per bus 2
3 2
Maintain Hot Shutdown".+
57.0 Hzn I
interlocked with P-7 and P-8 1
- 16. RCP Breaker Trip -
interlocked with:
i a.
P-7. 4 loops 4 breakers 2 3
2 Maintain flot Shutdown" +
H.A.
l b.
P-8. 4 loops 4 breakers 1 3
2 Maintain flot Shutdown".+
N.A.
i 4
l l
- 17. Low Steam Generator Level 2 per loop 1 per loop 1 0
Maintain Hot Shutdown".+
25% of narrow I
in coincidence with feed range instrument flow - steam flow mismatch 2 per loop 1 per loop 1 0
Maintain Hot Shutdown".+
span and mismatch of 60% of 3.495 x 10' lbs/hr (nominal 100%
1 s
steam flow rate).++
l l
TABLE 3.1-1 (Continued)
Reactor Protection System - Limiting Operation Conditions and Setpoints 205R-295 31 Amendment Nos, s
i
..,.. - _.. - - ~. -. - _. _ ~, -...
-en,,,,,.
,..-_,_,.,,_,.n,.
-.,_,-w.,,.,,,_,.,-,.~.
ELRMISSLVES 51If0IRI P-6 10-10,,p,### until Gamma Hetrics detectors are installed 10-5% Rated Power #### af ter Gamma Metrics detectors are installed P-7 10% Rated Neutron Flux and Pressure Equivalent to 10% of Rated Turbine Load P-8 28% of Rated Power ++
P-10 10% of Rated Neutron Flux ###
+ If minimum conditions are not met within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, the unit shall be in the Cold Shutdown condition within an additional 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
++ Setpoints are established tolerances for instrument channel and setpoint errors as specified in " Zion NSSS Setpoint Evaluation.
Protection System Channels, Eagle 21 version", Revision 1, April 1992. The instruments shall not be set to exceed a Limiting Safety System Setting.
For channel test. calibration or maintenance, the minimum number of OPERABLE channels may be reduced by one but to not less than one,
+++
and the minimum degree of redundancy may be reduced by one but to not less than zero, for a maximum of two hours. For Automatic Reactor Trip logic and Reactor Trip Dreakers. the allowable outage time is a maximum of eight hours.
When block conditions exist, maintain normal operation.
' Maintain Hot Shutdown' means maintain or proceed to Hot Shutdown within four hours if the unacceptable condition arises durino power operation.
Verif y shutdown margin immediately and comply with Section 3.2.1. A,B.
When blocked conditions exist, maintain normal operation.
- During Modes 3, 4 or 5 and with the Reactor Trip System breakers closed and the Control Rod Drive System capable of rod withdrawal, the following applies: With the number of OPERABLE channels one less than the Minimum OPERABLE Channels requirement, restore the inoperable channel to OPERABLE status within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> or open the Reactor trip breakers within the next hour.
- During Modes 1 or 2 with one of the diverse trip features (Undervoltage or Shunt Trip Attachment) inoperable, restore it to OPERABLE status within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> or declare the breaker inoperable and maintain or proceed to Hot Shutdown within four hours if the unacceptable condition arises during power operation. The breaker shall not be bypassed while one of the diverse trip features is inoperable except for the time required for performing maintenance and testing to restore the breaker to OPERABLE status.
- Setpoints are a established tolerances for instrument channel and setpoint errors as specified in " Channel Accuracies. Overall Channel Accuracies and Setpoint Tolerances for W NES Process I and C Reactor Protection and Control Systems" August 30, 1971 -
CEW-652. The instruments shall not be set to exceed a Limiting Safety System Setting.
- Setpoints are established tolerances for instrument channels and setpoint errors as specified in " Zion NS$$ Setpoint Evaluation Protection System Channels, Eagle 21 Version. Non-Westinghouse Channels, Revision 0, March 1993". The instruments shall not be set to exceed a limiting Safety System Setting.
TABLE 3.1-1 (Continued)
Reactor Protection System - Limiting Operation Conditions and Setpoints 205R-295 32 Amendment Nos.
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3.1 During a unit operation, the complete Almost all channels are supplied with sufficient instrumentation system will normally be in redundancy to provide the capability for channel service for that unit.
Reactor safety is calibration and test at power; the exceptions are provided by the Reactor Protection System, which backup channels such as reactor coolant pump automatically initiates appropriate action to breakers.
The removal of one trip channel on process prevent exceeding established limits.
Safety is control equipment is accomplished by placing that not compromised, however, by continuing operation channel bistable in a tripped mode; e.g., a with certain instrumentation channels out of three-out-of-four system becomes a two-out-of-three service since provisions were made for this in circuit.
The nuclear instrumentation system channels the plant design.
This specification outilnes are not intentionally placed in a tripped mode since limiting conditions for operation necessary to the test signal is superimposed on the normal preserve the effectiveness of the Reactor Control detector signal to test at power.
Testing of the NIS and Protection System when any one or more of the power range channel requires:
(a) defeating the oT channels is out of service.(1) protection CHANNEL SET that is being fed from the NIS channel and (b) defeating the power mismatch section The reactor protection system setpoints specified of Tavg control channels when the appropriate NIS in Table 3.1-1 are the nominal values at which channel is being tested.
However, the rate trips on the reactor trips are set.
The setpoint for a the remaining NIS channels still provide the reactor trip system or interlock function is dropped-rod protection.
Testing does not trip the considered to be set consistent with the nominal system unless a trip condition exists in a concurrent value when the "as measured" setpoint is within channel.
(2) the band (established tolerance) allowed for calibration accuracy.
The established tolerances for the Gamma Metrics P-6 interlock function are identical to the established tolerances for the (1)
FSAR Section 7.2.1 intermediate range neutron flux channels.
The (2)
FSAR Section 7.2.2 tolerances are identical since the P-6 Interlock function uses the same instrument channels and detectors as the intermediate range neutron flux channels. As such, the established tolerances for the intermediate range neutron flux channels apply for the P-6 interlock function.
t ZOSR-295 37 Amendment Nos.
__ = _ _.
+ If minimum conditions are not met within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, the unit shall be in the COLD SHUTDOWN condition within an additional 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
L Setpoints are i estabilshed tolerances for instrument channel and setpoint errors as specified in " Zion NSSS Setpoint Evaluation,
++
Protection System Channels, Eagle 21 Version", Revision 1. April 1992. The instruments shall not be set to exceed a Limiting Safety System Setting.
+++ This channel may be placed in the bypass mode during periods of active testing during safeguards equipment testing as specified in Section 4.4.2.
Setpoints are e established tolerances for instrument channel and setpoint errors as specified in " Channel Accuracies. Overall Channel Accuracies and Setpoint Tolerances for W NES Process I and C Reactor Protection and Control Systems" August 30, 1971 -
CEW-652. The instruments shall not be set to exceed a Limiting Safety System Setting.
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' Maintain Hot Shutdown' means maintain or be in HOT SHUTDOWN within four hours if the unacceptable condition arises during power operation.
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ENGINEERED SAFEGUARDS ACTUATION SYSTEM - LIMITING CONDITIONS FOR OPERATION AND SETPOINTS (Footnotes to Table) j TABLE 3.4-1 (Continued) i 20SR-295 131b Amendment Nos.
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