ML20024C548
| ML20024C548 | |
| Person / Time | |
|---|---|
| Site: | Davis Besse, Three Mile Island  |
| Issue date: | 04/20/1976 |
| From: | Lingenfelter J TOLEDO EDISON CO. |
| To: | |
| References | |
| TASK-02, TASK-06, TASK-2, TASK-6, TASK-GB EP-1202.04, GPU-2020, NUDOCS 8307120792 | |
| Download: ML20024C548 (11) | |
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1.1.1 Annuncistor' Alarms '
. . / 1. .At least two of the foer "APS CH 1(1.3.or4) CK TRIP alorss i's (*Q'd' J ~ t
'- (if not mann11y tripped).
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. 2. At least ena of the fo11ewLes starms-(if not manus 11y tripped).
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- 4. "f-0 MASTER TURB TRIr' (et 1.1.2 ' TodLvidual and red group in-timit itshts on.
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l'.1.3 Espid 4 crosse in reactor power (nsutron fiva level).
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1.1.4 Integrated Control system (ICs) in " track" moda.
. 1.2 A7tCMATIC MTf 0NS l',9N ' 1.1.1 All control rods, except the antal power shaping rods (ArsR's -
h!' groep 8) vill be fuity insertsd. *
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1.2.3 The turbine-Esoorstor win trip.
[
t g :.- 1.2.3 The ICs autor.atically transfers to the track modas matessins sc levet at low level Itait.
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1.2.4 the turblas bypass centrol valve setpotat for main stsaa header e lg$y.;
i , f, '. ,' '. pressure vill be changed to 995 peig.
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- , 9, 3 1.3 1 FerLfy that all sentrol rods ancept the Arst's are fully inserted.-
i ,p;- If not, meap ity trip the reactor.
- g. If not, mandalir 1.3.2 verify that the turbine-generator has tripped. . -' . . ,,1
!?.jT.. trip the tuttina. , ,
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[43 2 1.3.3 Cless the letdown testattoa velve. HU 28. t. >' .l '-Mis i l
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1.3.4 Maintain the pressortier levet above . lev levet heater interteck
- - @. If aesessary, start the second makeup pump.
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1.3.5 Verify that the turblue bypass vaivas are attempting to metatain main steam header pressure at 995 psis. If not, take s.sw al centrat Y,f ' . .
' et bypass valves,
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- ~ , 2 h 5 c ..k, ,.* . 1.3.6 ' Verify that tholCS is in track and thnt 'the (c'eduator flow to the
.0TSG's is reduced, Itcither tenb ator control station is sn-
~
-t
' '. ; "iland" manually reduce feedwater demand to scru. q 1.3.7 .12 the reactor power indications show any sign of an increase,
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taittato baron addition.
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M U !~.i 16 $UFP!TitENTARY ACTIONS d estions are occurring; if not.,
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1.4.1 Verify that tha follevteg take manuel control of too feedvator system.
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'. 1. The steen generator levels (startup levels LI 3r9A1, B1 on the control room " Feed Fusps" panel C-5711) are bcint maintained at
'; :jh' U[.
i the low level llait (30").
- 1. If all four reactor coolant pumps have tripped, the steem f . f,
- gestrator levels should be maiutsined at about $0*4 on the "q;,erste de Level Indication" (1.RS-5P9A,8 on the control room "Tecd. 1202.14 Pumps"
%
- panel C-5712), and the 1.oss of RC T10w - RC huop Trip, EF
- should 'es implestated.
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.;*s If tbt main feedwater pumps have1202.26, tripped, verif I
- 3.
I yi- d t the loss of SC Feedvater Emergency Procedure, EF T'r .
abould be impicaanted.
- i. p"; Maintain a etnimisa level of 18 inches onHakeup Tank Level" b 1.4.1 control roos "Resctor coolant Makeup and Pressurtzer Control" P panet C-5703). Add boric acid and primary water to the Makeup M .- Tank by tuttiating a batch addition as per section 5 of the noroa k' *, '. canoestration Contr4 Procedure, SF 1103.04.
j Wrg In this batch addition, both boric acid and primary (or M
Q,s;.
desinatalised)
F1-MD41 on passt C-5702 and total flow tros the tiidicator water are to be adde J
l P...e so the batch controller.
,, i ", 1.4.3 Implement EP 1202.03, Turbing Trip. The sections of EF 1202.03 tha
[g,C2 -
Pertals to the Esactor Coolant 8ystem may be deletsd.
it--- 1.4.4 Tarify that the turbine bypass valves sentrol main steam header"Throt Pre l
.1 pressure at approminately 995 psis (as per '
'O9 ^* eentrol roos "Ic8 and Reactor control" penel C-5710); if not, tak l
1 ;* :
i..V manuel sentrol veins " Turbine aypass Vaiv
' ' : .. seosssary) that the atmospheric exhaust valvas are open and the
.I ' ' ' listbite bypass valvee are closed. Thte etsp does not apply tf the -
7 g* .;.
STEC8 hea been 44tuated.
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I+4.5 Verify that the raatter epolant pressure returns to"the normalPR5-RC '
l N,;;.* operating pressure of 2155 pets asbrper "Ec p @Ml8 Pre T5 ",'M
! C-5705.
In esse of high pressure, verify that pross A L F i wated at 220$ peig (if roector coolant pumps are on) y1 power relief volve opens et 2255 psis: if not, tske i d. ((n c<ase _q.(,,
f., '" 's- of the pressuriser spray valve and power rettet valv t *R* E ters
~
low reacter coolant pressure, verify that the pressurT
,./~ - .
lett implement EP 1201.06, taas et Ec/ac Pressure.
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- 1.4.6 When"Recctor Coolatt Aversga Temperatura (as por TR-RC7 of TI-EC7
[ on control room "ICS and Reactor Control" panst C-5707) stabilizea
)2 . . .?
- and bestne to appressh 546'? (naturation temperatura for 995 paie.)
' ,i ' .k i redusa the pressuriser level setpoint to 100 inches using "PRER LtVEL" L10-RC14 on control roos "Resetor Coolant Hakeup and Pressuriser b*,, Control" paast C-5705, i'" "..'
f/D:
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1.4.7 Initiate the calculation of a reactor shutdeva r.argin se per 1103.15.
Section 8 of Reactivity Estance Celesistions, SP Q
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1.4.6 Verify that the source range nuclear instrumentatLor(" Log Count Rate" MT-1,2 en control room "1CS and Reactor control" panet c-5706) is
. a d.f-activated when the intermediate range nuclear instrussentation (" Log it" k.l[. 31-3,4 sasa panet) indicates 5n10-1 amps.
k.i.
Mi. .
' k.4.9 vben steady conditions have been reached with averste reactor sentant tsaperature at shout 516'F, initiate the investigation of rf ..-. ths cause of the trip. Reguest e Post Trip Review and sequence if lf
- g.. .c 1,.st. ett.to.t.
- - 1.4.10 Enter in the Operator's Log the isst available criticality informs.
tion includLas t. Lam, red position, boron concentration,' power level,
@) ' .
and RCS sverasa temperature.
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1.4.11 Refer to PP 1102.03, Trip Recovery Procedure, for a cocpletion of the cooldown to hot standby conditions and subsequent cooldown or startvy.
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'. ,71i r Only the Reactor Protection System (including the manual trip funettuni,)
[t g .x ' ,C D t o trip the reactor. The parsmettre conttored and the correspon&p, trip setpoints are described in SP 1105.01, Reactor Protcctiun tystem g J , . .., . -
'- Operettus Procedure.
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- i.' j ' ;* When the resotor is tripped the control rode (except group 8) fall by gravity into the core resviting in an Launedtato reduction of core powr t[-*k, k, ,' (powtr generally falle to about 5% of the initial power level and continvro
- to fall thercaftsr). When the Reactor Coolant System (RCS) heat source is
.pj ' ';Q .
'u thus comoved, the reactor coolant. oristnally at 582or, is cooled by the water in the steam generators at a temperature of 530'r (naturation t.,4 q. .- .
- tamparatute for 370 poig). As the coolant temperature decreases the total volume of toolant doctcsees and care aust be taken to prevent losing
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pressuriser level. At the son,a tizo the secondary steam pressuro (and
- ! I, .'* qonseguently the saturation temperature) is increasing ar..f, because the turbius stop valves have closed due to the turbine trip. depending on I
the initial power level, the pressure may cause the main steam safety
- N5* valves to open.
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When the reactor is tripped the Integrated Control System wLil transfer the main steam header pressure setpoint to a value of 995 pais (125 pst
%c3 c ;. - greater then normat) which increases the saturation tosperature of the jN.'y water in the steam generator and reduces the reactor coolant heat tois.
p I ;. f The 125 put bios on asia steam header pressure antpathe will be maintatoed i + until the reactor trip is resett consequently, a steady state condition vill be reached with storage reactor ecolant tempcrature at about 5'.6't' gW corresponding to the enturation temperature of the 195 psig main steam pressure.
4 .
d ,When the steady state condities is reached . a cooldown to 5300r is con-h*
k:;I'.
g*; ' docted as directed by the Trip Recovsry Procedure. PP H02.03, from which
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a normal rastert or a normal cooldewn may be initiated. '
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i This procedars applies primarily to reactor trips from powers greater than
. 1.57 For reactor trips free powers between 5 and 15% the procedure also P g;- lies with the exception that some autosatic actione (specifically spp.. -
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turbine trip and ICs going to "treck" node) say not occur, and the sato4 Lated operator actions say be deteced (specifically the initiatio.
n i/
-o [ M. - , 'ot the Turbine Trip guergency Procedure, SP U01.03.)
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%: ":.f,. , P 1. At least two of the four 8'RPS CH 1 (2.3. er 4) CH TRIP" alarms W.' g p . (12 not manus 11y tripped) ig, 2. At 1 cast one of the followtog alarms (if not ranually tripped).
3 L -* .T 1. **RP8 RC HI PRE 55 TRIP" V h 2. "RPS RC P.I TEMP TRIP" i A ."'.
! 4. RP3 CIHr HI FPISS 'IRIPd
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- 6. "RPS RC PPISS-TEMF TRIP"
- e i. 7. "RPS TLITX DTI.UX - PLOW TRIP"
. n.,.';, ' 6. "RP5 HI PLUX TRIP"
- f. ' 3. "CRD TRIP C0!!FIRN" ..
2.1,2 Indtvidual and rod group in-Ittit lights on.
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( ., 2.1.3 kapte decrease la reacter power (nsutron flux 1cve1}.
$, J .' '2. 2 Atr:0MATIC_ At rTONS
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. ~.b - 2.2.1 Al'1 control rods, except tha axial per$r shapins rods (APsa's - stoup 8
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.- will ba*fv11y losarted. -
,2.2.2 The' turbine bypass control valve setpoint for main secsa header h';'[. . ',
,,. .. pressure wilt be changed to 993 peig.
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2.3 . MDIArt AtfloRs C2.-
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- 3.3.1 vertfy that all control rods er. cept tiis APSR's ,are fully inserted.
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'2C mot, sanually trip the reactor. -.
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. P. 7.3.2 If the reactor pever indicattoca show any sisu of an tocrease, f.tf;,Q,,, LnLtLate boren s64Ltton. '
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2.3.3 Take sianual control of the turbine bypass valves (or atnesphoric
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vent volves) and control main steam header pressure to maintain
, 1. . 228 temperatura and pressuriser level at thete pre-trip concitions.
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2.4 $tTPPLEM:'NTAKY ACTIONS
- 1. ' . 2.4.1 Verify that the reactor coolant pressure returns to the normal i
operating pressure of 2155 pais as per RC NR Press" PF.$-ACIB on coatt roon "R44ctor Coolant Hahup and Pressurizer Control" panet C-5705. In case of high pressure, verLfy that pressuctact spray has actuated at 2205 psis (if reactor soolant pumps are on) and the pressuriser Op powerTeltofvalveopensat2255psigtifnot,takemanustcontro(
.'-- of the pressuriser spray valve and power roltof valve in ca.e ,g low reactor coolant pressure, verify that the f, ,9 u actutta to maintain prassure; if pressure and/pressur or resci y 3 f' lost implement EP 1202.04 Loss of r.c/RC Pressure. ,pd 'H. .
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- . A recctor trip from less than 37, power causes no appreciable transtents i s' s .' with the esccption that the turbine bypsis valves (or atmospheric vant E
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- 3. ~i talV6s) taill atterapt to control the main staca hisader pressure at 995 prig causing en inctsses in RCS tet:perature. Yer this reston. manual control I'
of the valves should be initiated to staintain stain etsam headte pressure L
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at a point to hold RC5 tcaporature and pressuriser icvel constant. L 4
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2.4.2 Initiato the calculation of a reactor shutdown martiu os per .
.- , section 5 of Reactivity Balance Calculottoito. SP 1103.15.
..4 i 2.4.3 Verify that the source range nuclear instrweentation (Log Count ;tute
'- W1-1, 2 ou control roca " ICE ond Reactor Control" psnet C-L706) le
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activated wh:n the intermediate range nuclear instruwentation(" Log H"
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HI-3.4 sama panel) indicatos 5 x 10-10 amps.
. 2.4.4. Tote sanual control of ths" Turbine grpass Valves"(or stasspheric -
i ?i vents) using PIC-ICS 12A, B on control room "1C5 end Re.setor
, Ni. - 't .. contre 1" panel c-5710. Maintain the turbine header pressure at P. .'" (or near) the saturation pressure for the RCS tosporature. (should
.. be near the pre-trip value).,
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I,' Y i l 2.4.3 when attedy state conditions have been re ched. initiate
' c; 1. - invcotigation of the cause of the trip.
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3,46 in the Opershor's Log record the last sval,labic criticality data 9' * ,
including time, rod positions, boron concentration, power level,
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sad RC8 toeperature. .
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2.4J Refer to PP 1102.03 Trip F.ecovery Procedure, to rer. urn the RCS to
' e : */ bot standby conditions. .
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/ EULI: Portions of PP 1102.03 neAd not he completed se directed .
[ W .' . by the shift Foremang specifically, those portions of the procedure dealtn5 with sscondary. plant equipment may r.ot o m- -
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