ML19308B200
| ML19308B200 | |
| Person / Time | |
|---|---|
| Site: | Oconee  |
| Issue date: | 05/03/1978 |
| From: | Reid R Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML19308B199 | List: |
| References | |
| NUDOCS 7912160078 | |
| Download: ML19308B200 (14) | |
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UNITE D STATLS NUCLEAR REGUt.ATORY COMMISslON
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WASIMNGT ON,0. C. 20,555 p,.. 2
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s...s DUKE P0tlER C0"PA!1Y DOCKET fi0. 50-269 0C0: LEE flUCLEAR STATI0fl, UtlIT ?!0.1 A!!EtlDitEllT TO FACILITY OPERATIflG LICEllSE Amendment tio. 61 License fio. DPR-38 1.
The t!uclear Regulatory Commission (tf e Ccemission) has found that:
A.
The application for amendment by Duke Power Company (the licensce) dated February 16, 1973, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Comnission's rules and regulations set forth in 10 CFR Chapter I; B.
The facility will operate in confo mity with the applicaticn, the provisions of the Act, and the rules and regulations of the Con. mission; C.
There is reasonable assurance ('i) that the activities authorizs-d by this amend.nent can be conducted without endangering the health and safety of the public, and (ii) that 'such activities will be conducted in compliance with the Commission's regulations; D.
The issuance of this amendment will not be inimical to the connon defense and security or to the health and safety of the public; and E.
The issuance of this amendment is in acc.crdance with 10 CFR Part 51 of the Cor. mission's regulations and all applicable requirements have been satisfied.
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Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendme.nt and paragraph 3.D of Facility Operating License No.
DPR-38 is hereby amended to read as follows:
3.B Technical Scecifications l
The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 61 are hereby incorporated in the license.
The licensee shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective as of the date of its' issuance.
FOR Tl!E NUCLEAR REGULATORY CCM:11SSION w) -l
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<. A,. // ' h l. d & : s
. i Robert W. Reid, Chief i
Operating Reactors Branch #4 Division of Operating Reactors
Attachment:
Changes to the Technical Specifications Date of Issuance: May 3,1978 e
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NUCLEAR REGULATORY COT.WISslON f.y i f.
(VAhlllNG T CN D. C. 205W^
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%,*.n A y DUKE PONER C0"PANY DOCKET fl0. 50-270 OCONEE NUCLEAR STATION, UNIT NO. 2 AMENDMErlT TO FACILITY OPFPATING LICEtiSE Amendment No. 61 License !!o. DPR-47 1.
The Nuclear Regulatory Comission (the Commission) has found that:
A.
The application for amandment by Duke Power Company (the licensee) dated February 16, 1978, complies with the standards and requirements of the Ato.nic Energy Act of 1954, as ar.anded (the Act), and the Commission's rules and regulations set forth in 10 CFR Chapter I; B.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Comission; C.
There is reasonable assurance (i) that the activities authorized by this caendnent can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance
'with the Commission's regulations; D.
The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Coraission's regulations and all applicable requirements have been satisfied.
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'2. I ccordingly, the'licenst. is amended by changes to the Technical A
- Specifications as indicated in the attachment to this license amendment and paragraph 3.B of Facility Operating License No.
DPR-47 is hereby amended to read as follows:
i i
- 3.8 Technical _ Scecifications A
The Technical. Specifications contained in Appendices A and B, as revised through Amendment No. 61, are hereby incorporated in the license.
The licensee shall operate 4
the facility in accordance with the Technical Specifications, i
f 3.
This license amendment is effective as of the date of its issuance.
FOR THE NUCLEAR REGULATORY C0:'lIISSION
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hobertW.Reid, Chief Operating Reactors Branch #4 Division of Operating Reactors
Attachment:
Changes to the' Technical Specifications Date of Issuance: ffay 3, 1978 I
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NUCLEAR REGULATORY COMMisslON f/
WASHING TorJ. D. C. 20555
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DUKE PO'.lER C0!'.PANY DOCKET f!0. 50-287 OCONEE f!UCLEAR STATIO.l, UNIT fl0. 3 AMEND'!ENT TO FACILITY OPERATING LICENSE Amendment No. 58 License No. DPR-55 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Duk' ?cwer Company (the licensee) dated February 16, 1978, complies with the standards and requirements of the Atomic Energy Act of 1954, as ansnded (the Act), and the Commission's rules and regulations set forth in 10 CFR Chapter I; B.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C.
There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangerina the i
health and safety of the public, and (ii) that such activities will be conducted in compliance with the Ccmmission's regulations; D.
The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E.
The. issuance of this amendment is in accordance with 10 CFR Part 51 of the Cocr.ission's regulations and all applicable requirements have been satisfied.
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2.
Accordingly, the license is amended by chances to the Technical Specifications as indicated in the attachment to this license amendment and paragraph 3.B of Facility Qperating License No.
DPR-55 is hereby amended to read as follows:
3.8 Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 58, are hereby incorporated in the license.
The licensee shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective as of the date of its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION g(bertW.Reid,Chieff' &.<.
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,..,4 l-Ro Operating Readtors Branch #4 Division of Operating Reactors
Attachment:
Changes to the Technical Specifications Date of Issuance: !!ay 3, 1978 e
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O ATTACitMEilT T0 LICEflSE AMEriDi1EilTS AMEtlD"Er4T !!0. 61 TO DPR-38 AMEf1DfiENT f!0. 61 TO DPR-47
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AMENDMEilT ?!0. 58 TO DPR-55 DOCKETS f05. 50-269, 50-270 AtlD 50-287 Revise Appendix A as follows:
Remove the following pages and insert revised identically numbered pages:
2.3 2.3-4 2.3 2.3-13 Changes on the revised pages are indicated by marginal lines.
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LIMITING SATLTY SYSTDI SETTINGS, PROTECTIVE INSTRU!ENTAT20N 2.3 Applicability Applies to instruments monitoring reactor power, reactor power inbalance, reacter cool:nt syste= pressure, rcactor coolant outict temperature, flow, number of pu=ps in operation, and high reactor building pressure.
Obicctive To provide automatic protective cetion to prevent any combination of process variables from exceeding a safety li=it.
Specification The reactor protective system trip setting limits and the permissible 1
channels shall be as stated in Table 2.3.lA-Unit bypasses for the instrument and 2.3-13-Unit 2 2.3-lC-Unit 3 Figure 2.3-2A-Unit 1 2.3-?B-Unit 2 2.3-2C-Unit 3 The pump conitors shall produce a reactor trip for the following conditions:
of Unit 1 (only) if power Loss of one pump during four-pump operation a.
level is greater than 80% of rated power.
Loss of two pumps and reactor power level is greater than 55% of rated b.
power.
Loss of two pumps in one reactor coolant icop and reactor power level is c.
greater than 0.0% of rated power.
d.
Loss of one or two pu:ps during two-pu=p operation.
Esses channels to monitor The reactor protective systes concists of four instrument each of several selected plant conditions which vill eeuse a reactor trip if any one of these conditions deviates fro: a pre-selected operating range
'.e the degree that a safety 11:10 may be reached.
The trip setting limi;o for protective system instrumentation are listed in The safety analysis has been based upon these protective Table 2.3-)A-Unir 1.
2.3-1B-Unit 2 2.3-lC-Unit 3 system instru=entation trip setpoints plus calibration and instrumentation errors.
Nucicar Overpower A reactor trip at hich power. level (neutren flu.0 in provided to prevent da-age te the fud1 c'
- in:: f r.,: teactiv!:
sur. lens too rapid to ba detected by pressure and te=perature ccasure.ents.
2.3-1
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i s k.onr i.xn ts !!ns. 61, 61, 58 l
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n During nor=31 plant cparation with all 'terecor coolant pumps operating, reactor' trip is initiated when the reactor power level reaches 105.5% of rated power.
Adding to this the possible variation in trip setpoints due to calibration and instrument errors, the =aximum actual power at which a trip would be actuated could be 112%, which is more conservative than the value used, in the saf ety analysis. (4)
Overpower Trio Based on Flow and I: balance The power icvel trip set point produced by the resetor coolant system flow is based on a power-to-flow ratio which has been established to acco==edate the most severe thermal transient considered in the design, the loss-of-coolant flow accident from high power. Analysis has deconstrated that the specified power-to-flow ratio is adequate to prevent a DN3R of less than 1.3 should a low flow condition exist due to any electrical malfunction.
The power level trip set point produced by the power-to-flow ratio provides both high power level and low flow protection in the event the reactor power level increases or the reactor ecolant flew rate decreases. The power level trip set point produced by the power-to-flow ratio provides overpower ONE pro-tection for all modes of pu=p operation.
For every flow rate there is a =axi-zum per=1ssible power icvel, and for every power level there is a minicu=
permissible icw flow rate. Typical power icvel and icw flew rate co=binations for the punp situtations of Table 2.3-1A are as follows:
1.
Trip would occur when four reactor coolant pumps are cperating if power is 105.5% and reaccer flow race is 1000% or flow rate is 94.8% and power level is 1000.
l 2.
Trip would occur when three reactor coolant pumps are operating if power is 78.8% and reactor flev rate is 74.7% or flow rate is 71.1% and power Icvel is 75%.
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3.
Trip would occur when one reactor coolant pump is operating in cach loop (total of two pumps operating) if the power is 51.7% and reactor flow rate is 49 C*. or flow rate is 46.4% and the power level is 49%.
The flux-to-flow ratios account for the maximum calibration and instrument errors and the maximum variation from the average value of-the RC flow ;.tgnal in such a manner that the reactor protective system receives a conservative indication of the RC flow.
For safety calculatiens the maximum calibration and instrumentation errors for the power level trip were used.
The power-imbalance boundaries are established in order to prevent reactor thernal limits f rom being exceeded.
These thermal limits are either power peaking kv/ft limits or DNSR limits.
The reactor powcr imbalance (power in the top half of cere =inus pewer in the botto= half of core) reduces the power level trip produced by the power-to-flow ratio such that the boundaries of Tigure 2.3-2.s Unit I are produced.
The power-to-flow ratio reduces the pewer i
2.3-23
- Unit :
2.3-20 Unit 3 2.3-2 Anendeents Noa. ! 61, -61,' 58 o
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1 lev 21 trip and assoble ted reactor power / reactor power-imbalcnco bouni:fsries by 1.055% for it flow reduction.
f Pump Monitors The pump r:onitors prevent the minimum core DNT.P. from decreasing below 1.3 by tripping the reactor due to the loss of reactor coolant purp(s). The circuitry rnonitoring pump operat ional status provides redun:: ant trip protection for DNS by tripping the reactor on a signt.1 diverse fiom that of the power-to-flow ratio. The pump monitors also restrict the power level for the number of pumpt in operation. The reactor trip upon loss of one pump during 4-pump operation above 801 FP is specified for Unit I in order to provide a rninfrum of 11.2%
DNDR margin in the flux / flow trip setpoint to z.:commodate the possible reduc-tion in thermal margin due to rod boning.
for units 2 and 3, loss of one pump trip is not rer uited becauw of thermal credits f rom excess RC flow, i.e., by maintainJnr. a rainimum RC flow of 109.5% for Unit No. 2 and 108.5% for Unit i
No. 3, respectively.
P.cactor Coolant System Pressure During a startup a cident from low poser or a slow rod withdrawal from high power, the system high pressure set point is rcsched before the nuclear over-power trip set point. The trip setting limit shown in Figure 2 3-1A.- Unit 1 2 3 Unit 2 2 3-IC - Unit.3 far h!gh reactor coclant system pressure (2355 psig) has been established to rnaintain the system pressure beloa the safety limit (2750 psis) for any design transient. (i)
The low pressure (1800) psig and variable low pressure (11.14 T
-4706) trip.
"I (1800) psig (l l.14T
-4706) setpointsshowninFigure2.3-1AhavebeenestablishedtomainU[EntheONS (1800) psig (ll.14T " -6706) 2.3-1B 2.3-1C ratio greater than or equal to 1.3 for
- se design accidents that result in a pressure reduction. (2,3) 7 Due to the calibration and instrumentation errors the safety analysis used a variable low reactor coolant system pressure tr ip value of (11.14 T
-47L6)
(11.14 T "I -4746)
(11.14 T "I -4746) out Coolant Cut let Ten.pera ture The high.cactor coolant outlet temperature trip setting limit (619"F) shown in Figi,re 2 3-1A has been established to prevent excessive core coolant 2.3-1B 2.3-lC temperatures in the operating range.- Due to calibration and instrumentation errors -the safety analysis used a trip set point of 620 F.
Reactor Building Pressure The hich reactor building pressure trip settinq limit (4 psig) provides r.os i t in t rurance th.i a. reactor trip wil1.C: cur in the unlikely eeent of aLic w u ccaiant-accicent, even in the abser.;e of a Icw reactor cc;isnt
-system pressure trip.
2.3-3 Amendsent" inn *..
61,L61, 58'
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- Shutdown Bypass in order to. provide for control rod drive tests, zero power physics testing, and startup procedures, there is provision for bypassing certain segments of the reactor protection system.
The reactor protection systen segments which can be bypassed are shown in Table 2.3-1 A.
Two conditions are imposed when 2.3-IB 2.3-1C the bypass is used:
l.
By administrative control the nuclear overpower trip set point rnust t,e reduced to a value <5.0t of rated power during reactor shutdown.
2.
A high reactor coolant system pressure trip setpoint of 1720 psig is automatically imposed.
The purpose of the 1720 psig high pressure trip set point is to prevent normal operation with part of the reactor protection system bypassed.
This high pressure trip set point is lower than the normal low pressure trip set point so that the reactor must be tripped before the bypass is initiated.
The over power trip set point of <5.0:1 prevents any significant reactor power from being produced when performing the physics tests.
Sufficient natural circulation (5) would be available to remove 5 0!! of rated power if none of the reactor coolant pumps were operating.
,5innie Loop 03eration Singic loop operation is pernitted only after the reactor has been tripped and 15-subject to the limitations set forth in Specification 3.1.3.
The RPS trip sctting limit: cnd permissible instrument channels' bypasses will be conf irrned prior to single loop operation.
REFE RE!!C ES (1)
FSAR, Section 14.1.2.2 (2) fSAR, Section 14.1.2.7 (3)
FSAR, Section 14.1.2.8 (4)
FSAR, Section 14.1.2.3 (5)
FSAR, Section 14.1.2.6 lhendo.Ms Nos. l61, 01, 53
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Table 2.1-1A D
Unit 1 3
c.
Pe,ac ter, Prote,r.,t ive *.yat es. Tr ip Set _t,Inc I. tat t a 49
- T*.
O e'a* Rearter
- u. s ro..r Peact s.r llorce Re irror rnalaat l'ae.*r e%.1 nt en pg f'aolant ramre firer.it lot. In Ch eir ' :' ' f '. P.
"I.crat I nr.
I' *'I' 3.a"r
'[
(e.g er a s f..r. Powc r (Isrcrat tnr. rever (eg ee st ing l' aver
. Shut ofewoo Rr$,Sc y nt, l'r)' R it e.1),,,
-7%?. R et c.1),,,,,
,4 9 *. Pate.1)
_Sypage s.C(1)
--o
- ,or icar r..wcr M.u.
In;.. s 10s.5
, in%.s a
(I Pste1)
-m W
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...-le.4r r.wcr t'.
. bee.1 8. nv. t i a-n ficw f.n n ts.., flow 1 On tt.e. ficw syra.ac.t c.i F1e w (.') and Iabaf.* nee.
c Ic.ea rc tuct Ia i
=tnog rco+ctIon saineem re.'oet t en
(* Teit e.?)
el.u-to I M lance
.t oe to la?.it.ince d.ee to f ehalance 1.
touclear rower Mi=.
Dam e.1 11 %
8f81 MT Byrma9ed P.
e it.n: tera. (t. pateet) ei.
4 titale React or Caolint 21M 23 %
21 %
1720 Svgtem l'rcesiste. raft. Nat.
tow Reactor Caolant 1800 1R00 1800 Bera=*cd u
Sy= tem Pseneurt. rate. Min.
- 8.. Varti 1e I.aw Peactor (ll.147
- 4706)UI (11.147
- 4 70'.)(
(ll.147
- 4706)
Bypasaed cut ont out Caalant Systen Preasure retr,. M!n.
'7.
Reactor Caalant T m r.
F., Mas.
619 619 689 619 M..Ittrh Reactor Butt.Itar.
4 4
4 4
Pregaurc, pale, M.iM.
- 11) T
.In in derrecs Falir^ntial t. (#F).
(?) Reactac Coctant Syst em riaw. 2.
(1) A.1,Inlettattvelv rantrolled reiluction get an t y d.sr t nr. reac epr stust etown.
( *. 4 A.tceittent!v get when attier gera. cit 9 of the P:*S are hwrange.t.
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Tahle 7.1-tit
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t'n t 1 fed.C.ter_Pfet er t.t ve T.yat en Trt p Set t t,ng 1.faitt3
- v.,
th e renctor 3
Caatant IVe rmer Feacter Three re.seter t'.atant is p=
t'rerattem in s
Coatant ru=r.
F.v< tr fr ep
{
etrera t Inc.
eteent inr.
Shutdow
(nperat g nr. r**er
(' Terat f.ic. raver (8ter*t:ct vi
-l'e:: N.it e.2 )
'.'72 Nat e.1)_
g a99_
-I DM.R.st e.1) rPS_Segmant D) m 105.5 1.0 lob's Ifd.5 l.
NucIcar rower it.is.
C4 8 '. P.s t e.!)
'Ne l ca r reve r Pt ig. Da9ed 1.0% t t aeg flaw I.0% t ir es flaw I.OM t in-= flew th r s = =ed 7 ~, (7) aa.t lahat.v.ce.
n t n..S r e.t... t f on m i n.'*
re.b.etlan etnus re.hertlen
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t o inh ;aare it.e-en tahil,-re d..- to tr hal mere G rate. p ME Syrm*9ed t'A
.elcar rower Mst. Ra sc.!
tlA 1
an I.-=;e %n t t er s. (% Rated) 17?C(
4.
!rh Pc-r t er Coolant Sy,t en 21 %
23 %
21 %
m l'resiure. rstr.. Han.
-w 1800 Ryra==eif e
1800 Iow Rearter Oca! ant Systrie.
1400 N
rec... r e. rale. Mt i.
- 4706)(1)
(11.14 T - 4706)(1)
Byrnseed
- 4706)(1)
(II.14 T t eut r.
- irt,ble le.w reactor Cactant (fl.14 7 o
a;st
y fi t e-t I'rceg.ere re tr. M f n.
619 639 619 7.
hartar Cantact Teer. F.,fi.n.
619 4
4 4
4
- r.. :. 8th Reacto-D.ellline lsessure, r=8g
- t.sa.
(t) T in in degreeg Fahrenbelt ( r).
" actar Caelant Sy=t r* Flew. 2.
..o
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(1? Maint at ret tvely cent entled reitection act 4 nl y. tier int. t enct ar rh.it.l..wn.
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8 '. ) kitanattrelly sat w' *n e ther actment 9 ef the rPS ara b y p;i s a e.t.
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,k TmStc 2.1-lC Unte 1 7
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Reacter FratertIve *:yat em,Tr t p,Se,t t,ing,f.1mi ty E
a fine Renet er rnne Reactar Tl.rce Reartar C.ml an t f* ump I3 E I"'l*9 Cnolant rumpg OperatInc, in C"."ra"t I nr.
Ogerattna Ese h 1, cop C7s.
Og c (skcratInc. Power (tiperattna rower (operatta Simt dawn
- t,$erj=ent
-I t9'7. Mateit)_
-75I Parel)
'MZ Pate.5),
_Rypa an_
1.
%.cicar Power Maw.
10'.3 105.5 105.5 3.0(1)
. us co
( 7 P.a t e.f )
7.
%.e! car rewar M e. Riaent 1.0% tteem flaw l.O*ns tl=e9 flew 1.0% t la** flew RyPa=*cd en Flev 12) en! Imbalance, ntn.,=
r e.t..c t t on minus re. ten-t ton utmeg r e.t.ec t t en t: Pat e t) eine to InSelance
.'ne to imi il an< e
<tne in tahalance 3.
mericar rewar M ex. ::aacJ NA NA 55%
Rypaneed ru g. %.n t t or *. (I Rat ed) e..,
11e.h Reacter Ccatant 2155 2155 2155 1720 N
4.
r w
'v-tem Tregsure. patr.. Min.
eC 5.
tow Pearter Cocient System 1800 1800 1800 Byrnesed reesaure, ra?g. Ntn.
- r.. Wir1,ble low Reactor C.w lant (ll.14 T - 4706)(1)
(ll.14 7 - 4706)(1)
(11.14 T - 4706)(1)
Pyra==ed "I
'.vate= rregante. pgig. Hin.
7.
"aaet er 'Caol ant Tewe.
F.,
619 619 619 619
- ta n.
't. tftr.h F* actor BullAlnr.
4 4
4 4
Prcamure, pstr., Mas.
(t) i.it 19 in fegeces Fatiranheit ("F).
o
(?) reactor Ccclant Syntem Flow. 2.
(1) Maintattattvely cantralle.1 trefortion de r einly dortnr. reactor pSit.fown.
(4).Autewittrally act when etteer screente of ti.* RPS mre I.yrasar.l.
.