ML20024C548

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Emergency Procedure EP 1202.04, Reactor Trip, Nuclear safety-related
ML20024C548
Person / Time
Site: Davis Besse, Three Mile Island  Constellation icon.png
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)
v • d • e


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1.1.1 Annuncistor' Alarms i's (*Q'd' J ~

.. / 1..At least two of the foer "APS CH 1(1.3.or4) CK TRIP alorss t

(if not mann11y tripped).

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At least ena of the fo11ewLes starms-(if not manus 11y tripped).

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1.1.2 ' TodLvidual and red group in-timit itshts on.

?.ad l'.1.3 Espid 4 crosse in reactor power (nsutron fiva level).

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Integrated Control system (ICs) in " track" moda.

1.1.4 1.2 A7tCMATIC MTf 0NS All control rods, except the antal power shaping rods (ArsR's -

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1.1.1

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groep 8) vill be fuity insertsd.

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1.2.3 The turbine-Esoorstor win trip.

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1.2.3 The ICs autor.atically transfers to the track modas matessins sc t

levet at low level Itait.

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1.2.4 the turblas bypass centrol valve setpotat for main stsaa header lg$y.; '.,' '.

pressure vill be changed to 995 peig.

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1.3 D o lftf.A"? i0710't8 I

, 9, FerLfy that all sentrol rods ancept the Arst's are fully inserted.-

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1.3 1 If not, meap ity trip the reactor.

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If not, mandalir

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1.3.2 verify that the turbine-generator has tripped.

trip the tuttina.

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[43 1.3.3 Cless the letdown testattoa velve. HU 28.

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1.3.4 Maintain the pressortier levet above. lev levet heater interteck If aesessary, start the second makeup pump.

(4c").

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Verify that the turblue bypass vaivas are attempting to metatain Oh,*k Y,f '..

main steam header pressure at 995 psis. If not, take s.sw al centrat 1.3.5 et bypass valves, T

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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-q

~

"iland" manually reduce feedwater demand to scru.

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.12 the reactor power indications show any sign of an increase, 1.3.7

~

taittato baron addition.

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M U !~.i 16 $UFP!TitENTARY ACTIONS d

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estions are occurring; if not.,

Verify that tha follevteg

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take manuel control of too feedvator system.

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The steen generator levels (startup levels LI 3r9A1, B1 on the

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control room " Feed Fusps" panel C-5711) are bcint maintained at 1.

i the low level llait (30").

If all four reactor coolant pumps have tripped, the steem gestrator levels should be maiutsined at about $0*4 on the "q;,erste f. f, 1.

Level Indication" (1.RS-5P9A,8 on the control room "Tecd. Pumps" de 1202.14 panel C-5712), and the 1.oss of RC T10w - RC huop Trip, EF should 'es implestated.

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If tbt main feedwater pumps have tripped, verif I

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1202.26, the loss of SC Feedvater Emergency Procedure, EF d

t T'r abould be impicaanted.

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Maintain a etnimisa level of 18 inches onHakeup Tank Level" i.

control roos "Resctor coolant Makeup and Pressurtzer Control" b

1.4.1 Add boric acid and primary water to the Makeup P

panet C-5703).

Tank by tuttiating a batch addition as per section 5 of the noroa M.-

k' *, '.

canoestration Contr4 Procedure, SF 1103.04.

In this batch addition, both boric acid and primary (or j

desinatalised) water are to be adde Wrg M

Q,s;.

F1-MD41 on passt C-5702 and total flow tros the tiidicator J

so the batch controller.

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1.4.3 Implement EP 1202.03, Turbing Trip. The sections of EF 1202.03 tha i

[g,C2 Pertals to the Esactor Coolant 8ystem may be deletsd.

1.4.4 Tarify that the turbine bypass valves sentrol main steam header"Throt Pre it -

.1 pressure at approminately 995 psis (as per eentrol roos "Ic8 and Reactor control" penel C-5710); if not, tak l

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manuel sentrol veins " Turbine aypass Vaiv l

1 ;* :

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seosssary) that the atmospheric exhaust valvas are open and the

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listbite bypass valvee are closed. Thte etsp does not apply tf the 7 g*.;.

STEC8 hea been 44tuated.

I+4.5 Verify that the raatter epolant pressure returns to"the normalPR5-RC I

  • I,

operating pressure of 2155 pets as per "Ec M Pre N,;;.

' T5 ",'M

@ l8 br p

l In esse of high pressure, verify that pross wated at 220$ peig (if roector coolant pumps are on)

A L F

C-5705.

y1 i

power relief volve opens et 2255 psis: if not, tske i d.((n c<ase _q.(,,

of the pressuriser spray valve and power rettet valv t *R* E ters f., '" 's-low reacter coolant pressure, verify that the pressurT

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lett implement EP 1201.06, taas et Ec/ac Pressure.

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EP 1201.04 1.4.6 When"Recctor Coolatt Aversga Temperatura (as por TR-RC7 of TI-EC7

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on control room "ICS and Reactor Control" panst C-5707) stabilizea and bestne to appressh 546'? (naturation temperatura for 995 paie.)

)

redusa the pressuriser level setpoint to 100 inches using "PRER LtVEL" 2...?

', '.k L10-RC14 on control roos "Resetor Coolant Hakeup and Pressuriser i

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Control" paast C-5705, 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 4 Y.'ij *:

Q 1.4.6 Verify that the source range nuclear instrumentatLor(" Log Count Rate" y-

,.s

.E.,

MT-1,2 en control room "1CS and Reactor control" panet c-5706) is activated when the intermediate range nuclear instrussentation (" Log it

. a d.f-k.l[.

k.i.

31-3,4 sasa panet) indicates 5n10-1 amps.

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 *

.c 1,.st. ett.to.t.

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1.4.10 Enter in the Operator's Log the isst available criticality informs.

@) '

tion includLas t. Lam, red position, boron concentration,' power level,

"i and RCS sverasa temperature.

1102.03, Trip Recovery Procedure, for a cocpletion of the 1.4.11 Refer to PP cooldown to hot standby conditions and subsequent cooldown or startvy.

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.u Only the Reactor Protection System (including the manual trip funettuni,)

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[t g.x ',C D t o trip the reactor. The parsmettre conttored and the correspon&p, trip g

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setpoints are described in SP 1105.01, Reactor Protcctiun tystem Operettus Procedure.

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When the resotor is tripped the control rode (except group 8) fall by i.

gravity into the core resviting in an Launedtato reduction of core powr t[- k,,'

(powtr generally falle to about 5% of the initial power level and continvro

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thus comoved, the reactor coolant. oristnally at 582or, is cooled by the

'u 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

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'i.

volume of toolant doctcsees and care aust be taken to prevent losing 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 the initial power level, the pressure may cause the main steam safety I

N5*

valves to open.

M:

When the reactor is tripped the Integrated Control System wLil transfer t, '.

a the main steam header pressure setpoint to a value of 995 pais (125 pst

%c3 ;. -

greater then normat) which increases the saturation tosperature of the c

water in the steam generator and reduces the reactor coolant heat tois.

jN.'y p I ;.

The 125 put bios on asia steam header pressure antpathe will be maintatoed f

until the reactor trip is resett consequently, a steady state condition i

+

g vill be reached with storage reactor ecolant tempcrature at about 5'.6't' corresponding to the enturation temperature of the 195 psig main steam W

pressure.

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, hen the steady state condities is reached. a cooldown to 5300r is con-d W

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docted as directed by the Trip Recovsry Procedure. PP H02.03, from which 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 For reactor trips free powers between 5 and 15% the procedure also

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lies with the exception that some autosatic actione (specifically f 'h.I.,.

spp..

P 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/

[ M. -, 'ot the Turbine Trip guergency Procedure, SP U01.03.)

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2.1.1 Annunciator Alsras

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At least two of the four 8'RPS CH 1 (2.3. er 4) CH TRIP" alarms (12 not manus 11y tripped)

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At 1 cast one of the followtog alarms (if not ranually tripped).

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2.

"RPS RC P.I TEMP TRIP" i

A."'.

3. "RPS HI TLUX/130 RCP Ott TRIP"

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RP3 CIHr HI FPISS 'IRIPd 5.

"RPS RC LO PKtSS TRIP"

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"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"

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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}.

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'2. 2 Atr:0MATIC_ At rTONS

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2.2.1 Al'1 control rods, except tha axial per$r shapins rods (APsa's - stoup 8

!i will ba*fv11y losarted.

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,2.2.2 The' turbine bypass control valve setpoint for main secsa header pressure wilt be changed to 993 peig.

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. MDIArt AtfloRs

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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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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

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228 temperatura and pressuriser level at thete pre-trip concitions.

    • 2 2.4 $tTPPLEM:'NTAKY ACTIONS
1. '.

2.4.1 Verify that the reactor coolant pressure returns to the normal operating pressure of 2155 pais as per RC NR Press" PF.$-ACIB on coatt i

roon "R44ctor Coolant Hahup and Pressurizer Control" panet C-5705. In case of high pressure, verLfy that pressuctact spray has actuated Op at 2205 psis (if reactor soolant pumps are on) and the pressuriser powerTeltofvalveopensat2255psigtifnot,takemanustcontro(

of the pressuriser spray valve and power roltof valve in ca.e,g actutta to maintain prassure; if pressure and/pressur f,

,9 f' low reactor coolant pressure, verify that the u

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or resci,pd

'H lost implement EP 1202.04 Loss of r.c/RC Pressure.

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A recctor trip from less than 37, power causes no appreciable transtents i s'

?.-)-[2..f.t with the esccption that the turbine bypsis valves (or atmospheric vant E

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talV6s) taill atterapt to control the main staca hisader pressure at 995 prig I'

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causing en inctsses in RCS tet:perature. Yer this reston. manual control

3. ~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.

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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 activated wh:n the intermediate range nuclear instruwentation(" Log H" HI-3.4 sama panel) indicatos 5 x 10-10 amps.

~

~

2.4.4. Tote sanual control of ths" Turbine grpass Valves"(or stasspheric

, N 't..

?i vents) using PIC-ICS 12A, B on control room "1C5 end Re.setor i

i. -

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).,

i.;r I,' Y i l 2.4.3 when attedy state conditions have been re ched. initiate

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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 including time, rod positions, boron concentration, power level, 9'

  • q.

sad RC8 toeperature.

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2.4J Refer to PP 1102.03 Trip F.ecovery Procedure, to rer. urn the RCS to

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bot standby conditions.

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EULI: Portions of PP 1102.03 neAd not he completed se directed

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by the shift Foremang specifically, those portions of the procedure dealtn5 with sscondary. plant equipment may r.ot o m-

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