ML20059D454
| ML20059D454 | |
| Person / Time | |
|---|---|
| Site: | Fermi  |
| Issue date: | 08/20/1990 |
| From: | DETROIT EDISON CO. |
| To: | |
| Shared Package | |
| ML19307A547 | List: |
| References | |
| NUDOCS 9009070046 | |
| Download: ML20059D454 (28) | |
Text
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t L1H1TlhG 5AFETY SYSTEM SETTINGS .
- *555
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REACTOR PROTECTION _ $JSTEM_ INSTRUMENTgjpH $ETP0]g,5 (Continued)
Avey,sge, a Power,RangeMonitor(Continued) ]s c
Because the flux distribution associated with unifom rod withdrawals does not
! involve high local peaks and because several rods must be moved to change power by a significant amount,ilibrium with the fission rate.the heat flux is in near equ In an rate of power assumed uniformrise is very sl rod withdrawal approach to the trip level, the rate of power rise is met Fore 4 than 5% of RATED THERMAL POWER per simi.e and the APRM system would be more than adequate to assure shutdown before the power could exceed the Safety Limit.
The IST neutron flux trip res.ains active until the mode switch is placed in the Run position.
The APRM trip syster. is calibrated using heat balant.e data taken during stehdy state conditions. Fission chenbers provide the basic input to the systera and therefore the monitors respond directly and quickly to changes due to transient operation for the case of the Fixed Neutron Flux-Unscale setpoint; i.e for a power increast the THERMAL POWER of the fuel till bit less than tha -
h/W ibdicated essociated withby the the neutron Y1ux fuel. For the Flowdue to the Biased L t atime constants
. Th.fH of athe meatI trans gi setpoint, time constant of 6 :t I seconds is introduced into thr. flow biased APRM in order to simulate the fuel thermal transient'characteri,ijcs. A sere conservative maximum value is used for the flow biased setpoint as shown in Table 2.2.1-1.
The APRM setpoints were selected to provide adequate margin for the Safety tirits and yet allow operating margin that reduces the possibility of unneces-sary shutdown. The flow referenced trip setpoint s'ust be adjusted by the specified formula in Specification 3.2.2 in order to aaintain these sargins when MFi.PD is greater than or equal to FRTP. For single recirculation loop operation, the reduced APRM setpoints are based on a A W value of 85. The A W value corrects for the difference in indicated drive flow (in percentage of driveflowwhichproducesratedcoreflow)betweentwoloopandsingleloop operation of the same core flow. The decrease in set 1oint is derived by '
multiplying the slope of the setpoint curve by 85. T1e High Flow Clamped Flow Biased Neutron Flux-High setpoint is not applicable to single loop operation as core power levels which would require this limit are not achievable in a single loop configuration.
- 3. Reactor Vessel Steam Dome Pyressure-High High pressure in the nuclear system could cause a rupture to the nuclear ,
system process barrier resulting in the release of fission products. A pressure l increase while operating will also tend to increase the power of the reactor by j compressing voids thus adding reactivity. The trip will quickly reduce the i neutron flux, counteracting the pressure increase. The trip setting-is slightly higher than the operating pressure to permit norsel operation without spurious 9009070046 900020 PDR ADOCK 05000341 P PNU-'
FEREI - UNIT 2 B 2-7 Amendment flo. 53 -
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3
. 7 4
i 3/4.3 INSTRUMEWTATION 3/4.3.1 REACTOR PROTECTION SYSTEM INSTRUMENTATION ,
i LIMITING CGWDITION FOR OPERATION '
3.3.1 As a minimum, the reactor protection systes instrume RESPONSE TIME as shown in Table -3.3.1-2.-
j APPLICABILITY: As shown in Table 3.3.1-1.
f g: M4
- V;O. tha number of OPERABLE channels less-than required t'(_Jea.25a4eaur WM I
- a. vain System requiremen1.fe- :
OPERABLE Channei. g r i - l/L iF6 systesM trip system in the tripped As place the inoperable ch e provisions of apnMir+4an 3.0.4 are
- m. .
I b.
With the number of OPERABLE channels less than required by the Minteum
) OPERABLE Channels per Trip System requirement for
' and take the ACTION required by Table 3.3.1-1.
SURVE!LLANCE REQUIREMENTS 4.3.1.1 Each reactor protection system instrumentation channel shall be demon-strated CPERABLE by the performance of the CHANNIL CHECK, fHANNEL FUNCTIO TEST, and CHANNEL CALIBRATION operations for the OPERATIONAL CONDIT the frequencies shown in Table 4.3.1.1-1.
4.3.1.2 LOGIC SYSTEM FUNCTIONAL TESTS and simulated automatic operation of all channels shall be performed at least once per 18 months.
l 4.3.1.3 The REACTOR PROTECTION SYSTEM RESPONS limit at least once per 18 months . Each test shall include at least one channel per trip system such that all channels are tested at least once every M times 18 months where N is the total number of redundant channels i specific reactor trip system. less
.&mf4
- im i;.:;:==hls channel need not be placed in the tripped conditinoperable ,
amt.
would cause the Trip F.a:t' N ** occurda -ta*-f t: Giami.e swL; M*hin P hours or the A channel shall be .3.1-1 for that Trip Function shall og L;..
E C'r:: -, e
- The trip system need not When be placed in the tripped condition if this would cause a trip system can be placed in the tripped a w .m O~ Tri,,en:ti: to occur. ""::ti:: to occur, place the trip system with-
- c. dition without causing tr.; Tri;;Ttripped condition; if both systems have the -
the most inoperable channels in thesame number of inoperable channels,/ pla condition. { ~/4 3 3-1 FERMI - UNIT 2
I Insert for Pg. 3/4 3-1 :
- a. With the number of TERABLE channels less than required by the Mininum TERABLE cht.nnels per Trip System requirement for one trip system:
- 1. Within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />, verify that each Functional Unit within the affected trip system _contains no more than one inoperable channel or place the inoperable channel (s) and/or that trip system in the tripped condition *.
- 2. If placing the inoperable channel (s) in the tripped condition would cause a scram, the inoperable channel (s) shall be restored to TEMBLE status within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> or- '
the ACTION required by Table 3.3.1-1 for the affected Functional Unit shall be taken.
- 3. If placing the inoperable channel (s) in the tripped condition would not cause a scram, place the inoperable channel (s) and/or that trip system in the tripped condition within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
The provisions of Specification 3.0.4 are not applicable.
i i
- An inopersle channel neeS not be placed in the tripped' condition where this would cause a scram to occur. In these cases, the inoperable channel shall be restored to TEMBLE status within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> after the channel was first determined to be inoperable or the ACTION required by Table 3.3.1-1 for that Functional Unit
~
j shall be taken.
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TABLE 3.3.1-1
, A REACTOR PROTECTION SYSTEN INSTIRSENTATION
=
E .
APPLICABLE MINIIRM j E OPERATIONAL OPERA 8tE CHfWWIELS l 1 Q FWETICImt. WIIT CONDITIONS PER TRIP SYSTEM (a) ACTISII
- 1. Intermediate Range IIonitors(b) j a. IIeutron Flex - High 2 3 1 l" 3, 4 3 2 5(c) 3(d) 3
- b. Insperative 2 3 1 I
3, 4 3 2
- 5 3(d)' 3 l 2. Average Feuer Range IIsni'm I 'I:
w a. IIeutron Flum - NfWe, Setdeun 2 2 1 1 . 3 2 2 y S/,ris.lefec/ 7/rerde//be, 5(c) 2(d) 3
- b. Fleu Blased Neuteen44em - Nigh 1 2 4
- c. Fined IIeutron Flum - Nigh 1- 2 4 L d. Insperative 1, 2 2 1.
- 3 2- 2 5(c) 2(d) 3 4
- 3. Reactor Vessel Steam Dome .
Pressure - Nigh ,
1,2(f) 2 1
- 4. Reacter Wessel Low IIster Level -
Level 3 1, 2 2 1
- 5. IInta steau Line Isoletten Valve - i Closure '1(g) 4 4
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.I y ,,,,f ii !
. _ . _ . ., , - _ . _ . .~. ., ,-- , . . . . . . -
a
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- , l a
TABLE 3.3.1-1 (Continued)-
REACTOR PROTECTION $YSTEM INSTRUMENTATION !
TABLE NOTATIONS hours for (a) A channel may be placed in an inoperable status for up to required surveillance without placing the trip system in the tripped
( condition provided at least one OPERABLE channel in the same trip system t
1s monitoring that parameter.
l This function shall be automatically bypassed when the reactor mode switch i -(b) is in the Run position.
(c) Unless adequate shutdown margin has been demonstrated per Specifica-tion 3.1.1, the " shorting links" shall be removed from the RPS circuitry ,
prior to and during the time any control rod-is withdrawn."
(d) When the " shorting links" are removed, the Minimum OPERA 8LE Channels Per Trip System is 4 APRMs, 6 IRMs and per Specification 3.9.2, 2 SRMs.
(e)- An APRM channel is inoperable if there are less than 2 LPRd inputs per level or less than 14 LPRM inputs to an APRM channel-(f) This function is not required to be OPERABLE when the reactor pressure vessel head is removed per Specification 3.10.1.
(g) This function shall be automatically bypassed when the reactor moda switch is not in the Run position.
(h) This function is not required to be OPERABLE when FRIMARY CONTAINMENT i INTEGRITY is not required.
(i) With any control rod withdrawn. Not applicable to control rods removed per Specification 3.9.10.1 or 3.9.10.2.
l (j) This function shall be automatically bypassed when turbine first stage '
pressure is < 154 psig, equivalent to THERMAL POWER less than 301 of RATED THERMAI POWER.
"Not required for control rods removed per Specification 3.9.10.1 or_3.9.10.2.
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t FERMI - UNIT 2 3/4 3-5 c 1
i YABLE 3.3.1-2 A REACTOR PROTECileN SYSTEN RESPONSE TffE5 E
e REspgNSE TIIE E
(seconds) _
4 FWCTISML WIT n *
- 1. Isvtermediate Range plenitors: m
- a. IIeutron Flum - Nip m .
i b. .insperative
- 2. Average Power Range IIsnitor*: -
m Neutron F1en - Engh, se i,,,u ta fed T),e,ni Pouni- )
- a.
Nigh / 6 i 1**
- b. Fhne Blased IIsotron44an < 9.99
- c. Flued IIeutron Fhat - Hip M
- d. Insperative ,
~ < 9.55
. 3. Reactor Wessel Steam Osse Pressure - Ni p 7 1.95
) 4. IIsacter Wessel Les Ideter Level - Level 3 7 9.95
. 5. Main Steen Line Isolatten Valve - Closure h J. 6. Kala Steam Line Radiatten - Nigh M
- 7. Brywell Pressure - Nip
- 8. Scram 91scherge Volume IInter Level - Ni p !
M
- a. Fleet Switch M
- b. Level Tranusitter -
< S.05
- 9. Tertine Step Valve - Closure 7 9.00***
i 11. Reacter Nede Switch Shutdeun Positten m ,
l k* 12. Itanuel Scran.
- 13. Deleted l
l I i
- Response time shell be asemered 4
g nHeutron detectors are enempt from response time testing.
from the detector output er from the input of the first electronic component in the channel.
" ** Including slaulated thereal power time constant.
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emeNeesured from deenergirstlen of K'-37 relay which inputs the turbine control valve closure slysel ;
l to the RPS.- .
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- ' - - , ,e-'~ _ _ . _ . - --___- - _ . _ _ _ _ _ _ _ - - _ . = - - _ _ _ _ _ _ _ . . _ - --__=_-.a'
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ifSLE 4.3.1.1-1 -
REACTOR PROTECTION SYSTEM INSTRUENTATION SURVElttJINCE E4WIMIENf5
. DWWWEL SPEM TIU M L e FUNCTIC#41. CWWWEL , CO W ITIONS FOR 1RII G 2 OWWWEL Call 8tATIGF ,)
CHECK TEST SURVElluueCE RE4 WIRES '
d FUNCT10 M L UNIT
- 1. Intermediate Range Montters: SMge),W 2 ,
M W M 2,3,4,5
- b. Inoperative t Average Pouer Range MonitorIII:
2.
SMIc ), W l 2 !
j a. Neutron Flux - SM,5,(b) SA W SA 3, 5 High, Setdown 5 sw ta ted !
! ** b. Flow Stased Neutron Therr;pQ N - High 5 g(c) y gd)(e) 5A,R(h) g.
l
- c. Fined Neutron Flux - SMICI,k M8I,5A 1 -!
High 5 M KQ M 1,2,3,5 .
Inoperative d.
l
- 3. Reetter Wessel Steen Dome Pressere - Nigh 5 :* Q cS R 1, 2
- 4. Reactor Vessel Low Water 'It' G g R 1, 2 Level - Level 3 5 g
h 5. Main Steam Line Isolation kQ R 1 Valve - Closure M g
- 9 IgI 2 6. Main Steen Line Radiation - R 1, I
? Migh 5 Jec Q 4 7. orywell pressure - Nigh 5 K Q,N R 1, 2 a
TABLE 4.3.1.1-1 (Continued) .
j REAC199 PROTECT 19N SYSTEN INSTMB U RAYBON GPERRTIGML SW WEILLAWIt'E REQBB
~ OtusEL OUWBEL CDlWilI8N5 FWR 18110B
- OWW8EL FUNCTI8 Bit TEST. CALIBRRTION SSMEILLANCE RE4WIREO CHECK E FWICTIONAL UNIT 3 8. Scram Discharge Valene lister Level,- Nigh 1.2.5(j)
Q R
- a. Fleet Settch IIR W Q(k) R 1. 2. 5(j) 5
- b. Level Transeltier R 1 M W GL
-9. Teettae Step Valve - Closure
- 19. Turblee Control Valve Fast MQ llh 1 Closure M
- 11. Seacter flade Softch M R M 1. 2. 3. 4. 5 Shutdama Positten 1. 2, 3. 4, 5 lh '98" W IGR l
w 12. ftennel Scram
- 13. Deleted -
w ~
4 (a) Bestren The 15 eMb.e may be encieded from OguBIEL CALIBRRTION.
and SWI channels shell he determined to overlap for_ at least % decadse daring each (b) startup after enterlag OPERATIGIglL COISITION 2 and the IRN and APWI channels shall be d everlap for at least % decades dering each controlled shutdoen. If est perfereed wittela tim pr
~
7 days.
(c) Within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> prior to startsy. If not performed within the proefoss 7 days.
This calibrettaa shall consist of the adjustaaet of the APWI chamael to confone to tem poser vet (d) calculated by a heat belance derfag GPERATICIIRL COMITISR 1 aben TIEWWIL poler > 25 of RAT PelER. Any MRI channel gota adjestment made la compliance w 18EWWIL POIER.'
lacleded in detenefalag the absolete difference.
[ (e) This calthrottaa shall coasist of the adjestment of the WWI f1om blamed chaenet to esefone to a g
g calibrated flee signet.The LPWIs shall be calibrated at least once per 1988 effective fell pseer tears (EFF g (f) estag the TIP system. -
F (g) Deleted.
' This calibretten shall coastst of verifylag the 6 i 1 second steelated therent pense time esastan h) This fonction is not regsfred to be OPElWWLE uhen the reacter pressere vessel head is removed
$ -((I) Spectficatlos 3.10.1.. Ilot applicable to centrol rods esmoved per. Spectffcation 3.9.10.1 or
-* (j) With any centrol red withdrase.
3.9.19.2.
yer{(Ec'aYio". e f_ # e hs'p se1poin f & the itIP un rY (K) IN(udes _
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IMITRUMENTATION 3/4.3.2 ISOLATION ACTUATION INSTRUMENTATION LIMITING CONDITION FOR OPERATION _
3.3.2 The isolation actuation instrumentation channels shown in Tabis 3.3.2-1 shall be OPFRABLE with their trip setpoints set consistent with th's values shown in the Trip 5etpoint column of Table.3.3.2-2 and with ISOLATION SYSTEN RESPONSE TIMi es shown in Table 3.3.2 3.
APPLICABILITY: As shown in Table 3.3.2-1.
ACTION:
l
- a. With an isolation actuation instrumentation channel trip eetpoint -
less conservative than the value shown in the Allowable Values column of Table 3.3.2-2 declare the channel inoperable until the channel isrestoredtoOfERABLEstatuswithitstripsetpointadjusted !
consistent with the Trip 5etpoint value.
- b. ber of OPERABLE channels less than required CPERABLE Channe stem requireme em L e f h piece the ino etab e channe' .e stem in tie tripped condition
- wi provisions o n 3.0.4
. ara-net-e le.
- c. With the number of OPERABLE channels less than required by the Minimum l OPERABLE Channels per Trip Systap4equirement for both tr'Ip systems, piece at least one trip system
- in the tripped condition within one l
! hour and take the ACTION required by Table 3.3.21.
, Msit parable channel need not be pieced in the tripped condition where
, woulc isolation to occur. In these cases, the inoperab nnel l shall be res OPERABLE status within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> or t N required by Table 3.3.2 1 for the Function shall be take
- The trip system need not be placed ripped condition if this would cause an isolation to occur. Wheni system condition without caus " solation to occu r (, p laced in the he trip tripped system with the most inoper annels in the tripped condition; i vstems have the.
se inoperable channels, place either trip system in <
% g-FERMI - UNIT 2 3/4 3-9 Amendment No. 41
. .l
.l Insert A Delete Section 3.3.2b and replace with the following: -
- b. With the nunber of TEmBLE channels less than required by the Mininum @EPABLE Chmnels per Trip System requirement for one trip system
- 1. If placing the inoperable channel (s) in the tripped condition would caise an isolation, the inoperable chenel(s) shall be restored to TERABLE status within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> or the ACTION required by Table 3.3.2-1 for the affecteu trip function shall be take7.
- 2. If placing the inoperable channel (s) -in the tripped condition would not c6use an isolation, the inoperable channel (s):
and/or that trip syste shall be placed in the trip 1*1 condition within a) 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> for trip functions conson to NS Instrunentation; and b) 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> for trip functions not conmon to NS
-Instrunentation.
The provisions of Specification 3.0.4 are not applicable.
Insert B
- Place one trip system (with the nost inoperable channels) in 'the tripped condition. The trip system need not be placed in the tripped condition when this would cause the isolation to occur. ;
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._~~~:-_______.- _ - . . _ _ - .. . - . _ . . . - . _ - . . . . , . . - . . . . . - . . . . . , , . . . .
TABLt_1.3.2=1 (Continued) l*. !$0LAT!0N ACTUATION INSTRUMENTATION
( '
ACTIONSTATEMENT$
ACTION 20 - Be in at least NDT SHUTDOWN within 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 next 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
ACTION 21 - Be in at least STARTUP with the associated isolation valves l
closed within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> or be in at least NOT 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 SHUTDOWN within the next'24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
ACTION 22 - 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 />.
l ACTION 23 - Close the affected system isolation valves within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> and declare the affected system inoperable.
ACTION 24 - Establish SECONDARY CONTAINMENT INTEGRITY with the standby gas i treatment system operating within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.
, ACTION 25 - Disable in the closed position the affected system isolation' valves within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> and declare the shutdown cooling mode of KHR inoperable. !
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 the j next hour and declare the affected system inoperable.
l ACTION 27 - Restore the manual initiation function to OPERABLE status l within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> or establish SECONDARY CONTAINMENT INTEGRITY ,
with the Standby Gas Treatment System operating. '
TABLE NOTATIONS j
- Whenhandlingirradiatedfuelinthesecondarycontainmentdurinkerea ALTERATIONS, or during operations with a potential for draining t CORE ,
_ vessel. {,
~ .
The high condenser pressure input to the isolation actuation instrumentation may be bypassed during reactor shutdown or for reactor startup when condenser ..
pressure is above the trip setpoint.
- Actuates dampers shown in Table 3.6.5.t-1.
(a) A channel may be placed in an inoperable status for up to hours for f I
required surveillance without placin0 the channel or tria system in the tripped condition provided at least one other OPERABLI cunnel in the same trip system is monitoring that parameter. In addition, for the NPCI i I
system and RCIC system isolation, provided that the redundant isolation valve, inboard or outboard, as applicable, in each line is OPERABLE and all required actuation instrumentation for that valve is OPERABLE, one i channel any be placed in an inoperable status for up to 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> for ,
required the surveillance tripped condition. without placing the channel or trip system in :
(b) Also starts the standby Sas treatment systaa.
{
(c) A channel is OPERABLE if 2 of 4 detectors in that channel are OPERABL (d) This level signal actuates Groups 2, 10, 11, 12, 14, 15, 17, 18, and ***.
(e) This level signal actuates Groups 4,13 and 15. ,;
2 FERMI - UNIT 2 3/4 3-14 Amendment No. 41
1 TABLE 3.3.2-1 (Continued) l ISOLATION ACTUATION INSTRUMENTATION TABLE NOTATIONS (Continued)
(f) Isolates with simultaneous RCIC Steam Supply Pressure-Low (Isolation Instrumentation) and Drywell Pressure-High (ECCS Actuation Instrumentation).'
(g) Isolates with simultaneous HPCI Steam Supply Pressure-Low (Isolation Actuation Instrumentation) and Drywell Pressure-High (ECCS Actuation Instrumentation).
(h) Reserved.
(i) Secondary Containment Isolation Push-buttons.
,(j) pressure signal actuates Groups 2, 12, 13, 14; 15, 16, 17, 18, and'
- With time delay of 45 seconds.
- #' These. hip %.of%ls) m c emmsn A> hk. 2PS tr# t%eNe n l
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FERMI - UNIT 2 3/4 3 Amendment No. 41 1
- . . . . - - . . . . - , , , . . . - - . . - - . . . - . - - - - . . . . . . . . . - . . . . . , . . - - . - - - - . . - - . . - , - , . ~ . . .
-i
. .. l ll, 1
n j a E ;
*d l = = mE = 5 == m a aE l .--
l d 6 d G Ga & g .g h _Sg
, em u, & ,m
- ! p
, # = +
4 lE e N , m a eE e E= mE e a mE l l s' l - I l
*p3 11 5 s n 8 =if f 1i'I 5"
I S $3. 8-u}.rjig 5 b ld
~
; .g pg Zu y 8 3 "A 3
,2 t j 3
"g.
j ,l j j I L3 C1 1eD s
, y .-.$.
M " M M Eg <f f W & g W4W E M M I B as a we eel - - - - - i a' - . FERMI - UNIT F . 3/4 3 21 Amendment No. !!, 41 L
s' ,
, -l
., TABLE 4.3.2.1-1 (Continued)
@ ISOLATIWS ACT1mTION INSTIENENTATION SOMEILIANCE - = -h i >
CIWuBEL W E M TIO Wit. I c UWWEEL FUNET191ML UWWEEL CWWITIONS ESR 155tII ;
} TRIP F 6 . CNECK TEST CAL 10RATIM SERVEILUWIE WIND 'l l 4. NIGI PEMMEF QP3tNIT IIIJECTICII SYSTEN ISOLATION
- a. IFCI Steam Line Flow - NigIn n
- 1. Bifferest.ial pressere 5 -#- Q R 1, 2, 3
- 2. Time Belay 11 4 -M- R R 1, 2, 3 I
- b. IDCI Steam Supply Pressure - Low S -M-G r'.. R 1, 2, 3
- c. IDCI Turbine Enlinest siapirmen Pressure - nigh 5 -#-@ R 1, 2, 3 -
== d. NFCI Equipment Room y 1 Tesqueretare - IHgh 5 *Q .R 1,2,3
,T e. Mutual Initiation IIR R Iul 1,2.3 i 5.- WW SV5THI _SINIDOIAI COOLIIW IBOE ISOtATION i
- a. Reactee Wesspel Leer Inster Level'-
Level 3- S -ft- m " R 1,2,3
- b. Gesctor Wessel (Shutdanes Cooling Cat-in Permissive laterlock)
, Pressere - IN $ $ -W-Q # R 1, 2, 3 l N c. IIunsel Initiation NR R RR' 1, 2, 3 l F't 7 5. SEEIRWMF GUITAIINENT ISOIATIWI
( { a. Reactor Wessel Law IIster Level - g' . 2 = Level 2 5 -R- Q R 1, 2, 3, and
- i g b. Bryuell Pressure - NiWe S +G8 R -
1,'2, 3 m
- c. Feel Pool Westilatisse Fuhamt .
Radiation - IN$ $ -M- Q R 1, 2, 3, and
- 1 I
- d. Ilmamel Initiation 13 R NR 1, 2, 3, and * ,i
!' O I, l
- 1 Anon hasuning'lerediated fuel in the secondary crataissent, during CORE ALTERRT1eII5, and during operations i with a poteettet for draining the vescter vesse,. ,
!t ** IIIy be bypassed usuler adsfalstrative centrol. j # Tecludes vers"+t< <.t% of the thpr setpoini & th e t'epo un<Y.
~
. b n
TABLE 3.3.3-1 (Continued) ,
~
.i EMERGENCY CORE COOLING SYSTEM ACTUATION INSTRUNENTATION ;
MINIMUM OPERABLE !
-6 E CHANNELS PER APPLICABLE Z TRIP OPERATIONAL
- TRIP FUNCTION SYSTEM (a) CONDITIONS ACTION g 1
to i I
- 4. AUTOMATIC DEPRESSURIZATION SYSTEMf
)
I
- a. Reactor Vessel Low Water Level - Level 1 2 1,2,3 30
- b. Drywell Pressure -'High 2 1,2,3 30
. c. ADS Timer 1 1,2,3 31
- d. Core Spray Pump Discharge Pressure '- High (Pemissive) 1/ pump 1,2,3 31 RHR LPCI Mode Pump Discharge Pressure High p e.
1/ pump 1, 2, 3 31 (Permissive)
- f. Reactor Vessel Low Water Level - Level 3 (Permissive) 1 1,2,3 31 ;
Manua1' Initiation 1/ valve 1, 2, 3 33 1 , R g. 1,2,3 31L
- h. Drywell Pressure - High Bypass Timer 2 T i. Manual Inhibit 1 1,2,3 33 4
-l r0, u .
. MINIMUM APPLICABLE TOTAL NO.- CHANNELS CHANNELS ^ OPERATIONAL OF CHAlelELS -TO TRIP OPERABLE- C0lWITIONS ACTION .
- 5. LOSS OF POWER
- 1. 4.16 kV Emergency Bus Under-voltage (Loss of Voltage) 2/ bus 1/ bus 1/ bus 1, 2, 3, 4** , 5** 35
- 2. 4.16 kV Emergency Bus Under -
5**
~
voltage (Degraded Voltage) 2/ bus 1/ bus 1/ bus 1, 2, 3,'4**, -35 { o -
.~ .
b.
- $ (a) A channel may be placed in an inoperable status for up to % hours for required surveillance without
" placing the trip system in the. tripped condition provided at least'one OPERABLE channel in the same E' trip system.is monitoring ~that parameter. ..
~
(b) Also. actuates the associated emergency diesel generators. i IN .(c) One trip. system. Provides signals to HPCI and RCIC suction valves. (d) One trip system. Provides signal to HPCI pump suction valves only.
'. (e) On 2 out of 2' logic, provides a signal to trip the HPCI turbine.
- When the system is required to be OPEPABLE per Specification 3.5.2..
** Required when ESF equipment is required to be OPERABLE.
# Not required to be OPERABLE when reactor steam done pressure is less than or equal to 150 psig.
N Inditedual. component controls. _ .. - . _- _ _ _ _ _ __ _ . _____ _ _____________ __ . _ _ _ _ _ _ . _ _ _ _m
4. TABLE 3.3.3-1 (Continued) EMERGENCY CORE COOLING SYSTEM ACTUATION INSTRUMENTATION ACTION STATEMENTS ACT]ON 30 - With the number of OPERABLE channels-less than required by the? ; Minimum OPERABLE Channels per Trip System requirement:
- a. For one trip system, olace that trip system in the trioped-
- condition within 15eer* or declare the associated ECCS inoperable.' N Aours, -
- b. For both trip systems, declare'the associated ECCS inoperable. ,
ACTION 31 - With the number of OPERABLE channels less than required by the - Minimum OPERABLE Channels per Trip System requirement, declare t
- the associated ADS Trip System inoperable.w/ fain d'y Acers.- l: [
ACTION 32 - With the number of OPERABLE channels less than' required by the Minimum OPERABLE Channels per Trip System requirr, ment, place the inoperable channel in the tripped condition within %Chourf- , R4 4 ACT]ON 33 - Restore the manual ini a on and/or manual inhibit' function to OPERABLE status within hours or declare the associated.ECCS or ADS Trip System. inoperable. ACTION 34 - With the number of OPERABLE channels less than required by the Minimum OPERABLE Channels per Trip System requirement, place at least one inoperable channel in the tripped condition within af WE houtf align the HPCI system to take suction from the suppres-sion pool, or declare the HPCI system inoperable. l ACTION 35 - With the number of OPERABLE; channels:
- a. One less than the Total Number of Channels, restore the inoperable channel to OPERABLE status within 72 hours or !
declare the associated emergency diesel generator: inoperable and take the ACTION required by Specification 3.8.1.1 or 3.8.1.2, as appropriate. . i
- b. Less than the Minimum Channels OPERABLE requirement, declare the associated diesel generator inoperable and take the-ACTION required by Specification 3.8.1.1 or 3.8.1.2, as appropriate.
W I 4 "The provisions of Specification 3.0.4 are not applicable. A 4 3/4 3-26 Amendment No. 35 t FERMI - UNIT 2 4
* , . , .,,,r , , , - , - , , - - - ---nv ,-
a l TABLE 4.3.3.1-1 A EERGENCY CORE COGt1NG SYSTEN ACitmTION INSTRtSENTATION SURVERLANCE REqutRUENTS . E CHANNEL OPERATIONAL
' FUNCTIONAL CHAfRIEL COMITIONS FOR 18tICH
- CHANNEL E TRIP F W CTION CHECK TEST CAtl8 RATION SURVEILLANCE REQUIRE 9 i [ 1. CORE SPARY SYSTEN
- a. Reactor vessel Low Water level -
Level 1 5 AQpg u R 1, 2, 3, 4*, 5* j b. Drywell Pressure - Nigh 5 kQ R 1,2,3 !
- c. Reactor Steam Dome Pressure -
i Low 5 M Q.g y R. 1, 2, 3, 4*, 5* '
- d. Manuel Initiation NA R IIA 1, 2, 3, 4*, 5*
- 2. LOW PRESSURE C00Uuff INJECTION NDDE OF RHR SYSTEN
- a. Reacter Wessel Lew Water Level - gy i Level 1 5 Ek Q R 1, 2, 3, 4*, 5*
w b. Drywell Pressure - Nigh 5 #Q## - R 1,2,3 1 c. Reacter Steam Dome Pressure - p p. . ~ w tow 5 *Q R 1, 2, 3, 4*, 5* O d. Reacter Vessel Lew Water. I Level - Level 2 5 WQ" R 1, 2, 3, 4*, 5* !
- e. Reactor Steam Dome Pressure - #m Low 5
- GL R 1,2,3,4*,5* .
- f. Riser Differential Pressure - y, Nip .
5 WQ R 1, 2, 3 ,
- g. Recirculation Pump Differential Pressure - Nigh 5 $V Q.gp R 1, 2, 3
{ h. Noneel Initiation IIA R N4 1, 2, 3, 4*, 5*
- 3. NIGNPRESSUREC00LNffINJECTIONSYSTEl[
i
- a. Reacter' Wessel Low Water Level -
Level 2 5 WQp R 1,2,3 ' i.
- b. Drywell Pressure - Nigh 5 3t'G? d# R 1,2,3 4
c.' Condensate Storage Tank Level - :
~Lew : 5 Jt-Q f *, R 1,2,3- a
- d. Segeressten Pool Water Level -
Nigh 5 WQ #g R 1, 2, 3
- e. Seector Vessel Ni p Water Level -
Level 8 5 #Q.Fg - R 1, 2, 3 ,
- f. Manuel Initiation IIR R NR 1,2,3
!__________________________________________--__-- -. . _ _ _ _ _ . .~ . , - - , , . - - - - , -
TABLE 4. _.3.1-1 (Continued) , l M E ENERGENCY CORE COOLING SYSTEM ACTUATION INSTRUNENTATION SURVEILLANCE REQ CHANNEL OPERAT10mL FUNCTIONAL CHANNEL ColR)lTIONS FOR WICM CHANNEL E CHECK TEST CALIBRATION SURVEILLANCE REQUIRED Z TRIP FUNCTION , m .
- 4. AUTOMTIC DFPRESSURIZATION SYSTEMF
- a. Reactor Vessel Low Water Level - & G2 R 1, 2, 3 .
Level 1 5 WQ R 1, 2, 3 Drywell Pressure - High 5
- b. WQ R 1, 2, 3 NA
- c. ADS Timer
- d. Core Spray Pump Discharge Pressure - High 5 W & ** R 1, 2, 3
- e. RHR LPCI. Mode ~ Pump Discharge Pressure - Nigh 5
- Q ,, R 1,2,3 -
Reactor Vessel Low Water level - g ; t' f. Level 3 5 WR , R 1, 2, 3 1, 2, 3 MA R NA Y g. Manual Initiation- gg ;f
$ h. Drywell Pressure - High Bypass *Q ,R 1,2,3 Timer M NA R- NA 1, 2, 3 .y,
, i. Manual Inhibit a: ; t a i 5. LOSS OF POWER - 1
- a. 4.16 kV' Emergexy Bus Under--
voltage (Loss of Voltage) . M R 1, 2,.3, 4**, 5**
- NA (Division 1 and Division 2) l
[ b. 4.16 kV Emergency Bus Under-. f voltage (Degraded Voltage) 5** a NA N R' 1, 2, 3, 4**, 2 (Division 1 and Division 2) 5
*
- When the system is required to be OPERABLE'per Specification 3.5.2.
* ** Required OPERABLE when ESF equipment is required to be OPERABLE. ;
Not required to be OPERABLE when reactor steam done pressure is~less than or equal to 150 psig. Include; veri $cc<% of _ ffre. . trip gefoMf of Me- hQr tenit. 8
## f .
r
. - . , , ,..----r
,.c .s .,+ 4c3 -- -y _ _ _ _ , , y ___--
..J.u' hap.,
t TABLE 3.3.5-1 REACTOR CORE ISOLATION COOLING SYSTEM ACTUATION INSTRUNENTATION . MINIMUM g OPERABLECHANNEL{,) PER TRIP SYSTEM ACTION
- FUNCTIONAL UNITS ,
" 2 50
- a. Reactor Vessel Low Water Level - Level 2
- b. Reactor Vessel High Water Level - Level 8 2(b) 50
- c. Condensate Storage Tank Water Level - Low 2(c) 51 l 1/ valve 52 ;
I d. Manual Initiation r
-i i 6 A chan wl may be placed in an inoperable status for up to X hours for required surveillance without i' (a) l g placing the trip system in the tripped condition provided at least one other OPERABLE channel in the '
- same trip system is monitoring that parameter.
[ (b) One' trip system with two-out-of-two logic. (c) One trip system with one-out-of-two logic. i , f i
. -- . ,. - .~
- _ = _ _ _ _ _ _ - _ _ _ _ - .- _ _ _ - _ _ _ _ _ _ _ - _ _ --
1 I l
)..
^
TABLE 3.3.5-1 (Continued) REACTOR COPE ISOLATION COOLING SYSTEM ACTION STATEMENTS ACTION 50 - With the number of OPERABLE channels less than required by the Minimum OPERABLE Channels _ per Trip System requirement:
- a. For one trip system, place the inoperable channel (s) and/or that trip system in the tripped condition within i l l
2.1 + hous or declare the RCIC system inoperable. l l
- b. For both trip systems, declare the RCIC system inoperable. .. ,l ACTION 51 -- With the number of OPERABLE channels less than required by the Minimum OPERABLE Channels per Trip System requirement, place at least one inoperable channel in the tripped condition I within ours or align RCIC to take suction from the suppres- l' sion or declare the RCIC system inoperable. i ACTION 52 - Restore he manual initiation function to OPERABLE status within
- hours or declare the RCIC . system inoperable. i l-
.:21
)l l
l "The provh socification 3.0.4 are not applicable. l l (.
.)
l FERMI - UNIT 2 3/4 3-38 l-l l !
~
TABLE 4.3.5.1-1 5 E
~
e REACTOR CORE ISOLATION COOLING SYSTEN ACTUATION INSTRUENTATION SUR E CHANNEL N CHANNEL FUNCTIONAL CHANNEL
** TEST CALIBRATION CHECK FUNCTIONAL UNITS Reactor Wessel Low hter Level -
g
- a. S E. Q R
-Level 2
# R S W (Q
- b. ~ Reactor Vessel High idater ,
Level - Level 8
- c. Condensate Storage Tank Level - Low 5 WQ 4 R R NA NA
- d. Manual Initiation T
8
# Lelude.s ver:FicaMn af the fr p s e tr<ini -F & h >;o u m 1- P 9
e W V t.
TABLE 4.3.6-1 CONTROL R00 BLOCK INSTRUNENTATION SURVEILLANCE REQUIRENENTS ' +
}
1 OPERATIONAL '
~ CHANNEL CHANNEL. COIR)ITIONS FOR WHICM
' CHANNEL FUNCTIONAL IEST CALIBRATION (a) SURVEILLANCE REQUIRED CHECK E TRIP FUNCTION
- 1. R00 BLOCK NOMITOR 1*
" NA Q
- a. Upscale 1* i b.
c. Inoperative Downscale NA NA S/U((b)S/U(b). S/U b),1. Gt Mg NA Q .Q 1*
- 2. APRM
- a. Flow Biased Neutron Flux - SA 1 '
High 5 S/U((b) MQ 1,2,5 NA
- b. Inoperative NA S/U(b),X st 3g y
- c. Downscale 5 S/U(b),g S/U b),% g e SA 2, 5 ,
- d. Neutron Flux - Upscale, Setdown' S ,
w 3. SOURCE RANGE MONITORS 2***, 5 NA S/U((b) S/U b),W W Detector not full in NA 5
- a. SA 2***,
Upscale 5 , Y b. NA 2***, 5 i 8, c. Inoperative NA S/U b ,W 2***, 5 5 S/U ,W SA
- d. Downscale
- 4. INTERMEDIATE RANGE MONITORS 2, 5 NA
- a. Detector not full in NA S/U((b) W b), SA 2, 5
- b. Upscale S S/UID},W 2, 5 NA S/U NA 4 c. Inoperative S/U(b),W ,W SA 2, 5
- d. Downscale -5
- 5. SCRAM DISCHARGE VOLUME 1, 2, 5**
NA R Water Level-High Q Z, 5**
- a. R MA Scram Trip Bypass NA b.
- 6. REACTOR COOLANT SYSTEM RECIRCULATION FLOW S/U ,E G Q 1 l
- a. Upscale . .NA N "A I Inoperative NA
- b. S/U(b)'R S/U Q Q 1 .
- c. Comparator NA ,
- 7. REACTOR MODE SWITCH R MA 3, 4 NA SHUIDOWN POSITION
i GENERAL ELECTRIC C0MPANY l l AFFIDAVIT j - 1 1, David J. Robare, being duly sworn, depose and state as follows: )
- 1. I am Manager, Plant Licensing Services, General Electric Company, and have been delegated the function of reviewing the information described !
in paragraph 2 which is sought to be withheld and have been authorized to apply for its withholding. ' i
- 2. The information sought to be withheld is contained in the report entitled
" Technical Specification Improvement Analysis for the Emergency Core !
Cooling System Actuation Instrumentation for Enrico Fermi Atomic Power l Plant, Unit 2," RE-014, Revision 1, July 1990. ;;
- 3. In designating material; as proprietary, General Electric utilizes the de-
-finition of_ proprietary information and trade secrets set forth in the American Law Institute's Restatement of Torts, Section 757. This definition provides:
"A trade secret may consist of any formula, pattern, device or compilation of information which is used in one's business and which gives him an opportunity to obtain an advantage over competitors who do not know or use it.... A substantial element of secrecy must '
exist, so that, except by the use of improper means, there would be difficulty in acquiring information.... Some factors to be considered in determining whether given information is one's trade ; secret are: (1) the extent to which the information is known outside l of his business; (2) the extent to which it is known by employees i and others involved in his business; (3) the extent of measures taken by him to guard the secrecy of the information;-(4) the value of the information to him and :a his competitors; (5) the amount of y effort or money expended by him in developing the information; (6) the ease or difficulty with the which the information could be properly acquired er duplicated by others."
- 4. Some examples of categories of information which fit into the definition of proprietary information are: ;
- a. Information that discloses a process, method or apparatus where i prevention of its use by General Electric's compei.itors without license from General Electric constitutes a competitive economic advantage over other companies; l
- b. Information consisting of supporting data and analyses, including ,
test data, relative to a process, method or apparatus, the application of which provide a competitive economic advantage, e.g., by optimization or improved marketability; t i f n
i i e i
- c. Information which if used by a competitor, would reduce his expenditure of resources or improve his competitive position in the l design, manufacture, shipment, installation, assurance of quality or i licensing of a similar product; j l
- d. Information which reveals cost or price information, production i capacities, budget levels or commercial strategies of General )
Electric, its customers or suppliers;
- e. Information which reveals aspects of past, present or future General i Electric customer funded development plans and programs of potential !
commercial value to General Electric;
- f. Information which disclo:es patentable subject matter for which it !
may be desirable to obtain patent protection;
- g. Information which General Electric must treat as proprietary according to agreements with other parties, f
- 5. Initial a) proval of proprietary treatment of a document is typically made by the Su]section manage
- of the originating component, who is most likely to be acquainted with the value and sensitivity of the information in relation to industry knowledge. Access to such documents within the Company is limited on a "need to know" basis and such documents are clearly identified as proprietary.
- 6. The procedure for approval of external release of such a document typically requires review by the Subsection Manager, Project Manager, Principal Scientist or other equivalent authority, by the Subsaction Manager of the cognizant Marketing function (or delegate) and by the Legal Operdion for technical content, competitive effect and determination of the accuracy of the proprietary designation in accordance with the standards enumerated above. Disclosures outside General Electric are generally limited to regulatory bodies, customers and potential customers and their agents, suppliers and licensees then only with appropriate protection by applicable regulatory provisions or '
proprietary agreements.
- 7. The document mentioned in paragraph 2 above has been evaluated in accordance with the above criteria and procedures and has been found to contain information which is proprietary and which is customarily held in confidence by General Electric.
- 8. The information to the best of my knowledge and belief has consistently been held in confidence by the General Electric Company, no public disclosure has been made, and it is not available in public sources. All disclosures to third parties have been made pursuant to regulatory provisions of proprietary agreements which provide for maintenance of the information in confidence.
l m
- 9. Pub'ic disclosure of the information sought to be withheld is likely to '
ca:Lse substantial harm to the competitive position of the General Electric Company and deprive or reduce the availability of pr' fit making o/portunities because it would provide other parties, including
'.,ompetitors, with valuable information regarding the application of reliability based methodoloa to BWR instrumentation. A substantial effort has been expended by" General Electric.to develop this information ,
in support of the BWR Owners' Group Technical .tpecification Improvement
- Program.
STATE OF CALIFORNIA ) COVNTY OF SANTA CLARA ) ss: , David J. Robare, being duly sworn, deposes and says: That he has read the foregoing affidavit and the matters stated therein are true and correct to the best of his knowledge, information, and belief, j Executed at San Jose, California, this I day of , 199 0 . T ULY David J. Robare General Electric Company Subscribed and ' worn before me this Y day of,$u).4 199,Q, U ' l ^^^^ h -.
...j h_ (n Y, Q
' ^ NOTARY PUBLIC, STATE OF CR.lFORNIA l
' To,:['; ,
, ,' A " A T H
- AuroftNIA "3 e,g g j %. ,,, ' l 84.' hts APR 8,1994 .
. . ~. .m _
OdCIAdek [ [ f Hussey > tJ3tA %puc. .caprog '
- P.i" p ,y,4,, ,
i __. _}}