ML20039C226

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0 to Emergency Procedure 1202-4, Reactor Trip.
ML20039C226
Person / Time
Site: Three Mile Island Constellation icon.png
Issue date: 03/13/1981
From:
METROPOLITAN EDISON CO.
To:
Shared Package
ML20039C225 List:
References
1202-4, NUDOCS 8112290079
Download: ML20039C226 (14)
v • d • e


Text

FOR USE ~lN' UNIT I ONLY g 2;4 ,, ,o THREE MILE ISLAND NUCLEAR STATION UNIT N0. 1 EMERGENCY PROCEDURE 1202 4 REACTOR TRIP Tacle of Effective Pages Page Revision Page Revision Page Revision Page Revision 1.0 19 2.0 19 3.0 20 <

4.0 20 5.0 20 6.0 20 7.0 20 8.0 20 9.0 20 10.0 20 11.0 20 N 12.0 20 D

Unit 1 Staff Rec pproval m

Approval ., ate Co a g ept. Heao v

Unit 1 PORC Recommends Approval shCnairman of &L s

PORC Date 3 2ff/

Manag TMI I App oval W93lm 1

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Date h# b '$$

QA Modifications / Operations Mgr

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/// Date e112290079 811224 N^

o R Document ID: 0015N IN UNIT i ONLY

~ ~ --

FORUFC

FOR USE IN UNIT I ONLY BMoosg THREE MILE ISLAND NUCLEAR STATION UNIT NO.1 EERGENCY PROCEDURE N0.1202-4 Reactor Trip 1.0 Svmotoms -

1. Reactor trip alarm due to any of the following: i (Actual trip set f

points are in parentheses).

a. Neutron Power 2 105.5 percent of rated power (1 b er-cent). >

e t on 75

c. Neutron Po ' 91 cercent of rate ow during operation l with .5 percent) operating per loc .9 ,
d. Loss reactor coolant 5 one reactor coolan*

e.

~

L of one or two r ant pumps dur' g two-pump -

operation.

f. Reactor coolar re 2 23C0 PSIG. 2(4*IG)  !
g. R? actor co nt r sure 5 1900 PSic -

PSIG) l

h. Rear,tcr L'2 ' pressure 5 (ll." T us - 103) (11.75 Tout

- 50 Y Re

i. e olant outlet temperature 2 619'F. (618'F) j.

Reactor building pressure 2 4 PSIG. (3.15 PSIG)

k. Manual reactor trip actuation.
1. Turbine Trip if >20 percent power.
m. Trip of both Main Feedwater pumps if > 10 percent power.
2. Individual and group "In Limit" lights actuate.

r 1.0 EOR UFF !N UNIT I ONI.Y

FOR USE IN UNIT I ON _Y !5?;ionig

3. Rapid decrease in Neutron Level indicated by Nuclear Instrumen- '

tation.

4 Main , turbine master trip energized alarm.

5. Rapid decrease in Unit Load.
  • 2.? Imediate Action A. Autematic Action
1. All rods insert (Except Group 8).
2. Turbine trip, stop valves close, generator eak open.
3. Source range high voltage energizes at 5 - " amp on .

NI-3 or 4

4. Turbinebfb . lves open.

! NOTE : ( oshericRebef a esM11chnifsteam  !

! M27 PSI.

kner tor pressure r,ach  !

(, 5. r Trip Contain ion occurs (M '*V3 closes isolating letdown).

B. Manual Action

! NOTE: The r* ,eters indicated by a a . sk will be  !

! 'o as the first s low-up action.  !

1. M t. p the reactor and that all rods are insert d except Group 8 by observing the green in-limit lights. If one or more rods are stuck out comence emer- ,

gency boration. I

2. Trip the turbine, verify that the turbine stop valves are I closed and that the generator breakers are open and start j lift pumps and turning gear oil pump.

{

s 2.0 FOR USE IN UNIT l ON LY

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FOP USE IN UNIT I ON _Y 1202-4 Revision 20

  • 3. Monitor pressuri:er level and maintain level greater than or equal to 100" . Start second make-up pump, MU-PlA, and open MU-V217. If the make-up system was not in the normal lineup, verify suction and discharge path and start a second make-up pump. '# make-up tank level reaches 55 inches, shift pump

/

suction to the BWST by opening MU-V14A and closinQt ' 2, until MU-T1 level is > 66".

  • 4 If reactor power is not less than 10 percen ith{poneminute following the reactor trip, commence e nrg boration.

r

5. Verify that 4)TSG level is decreasing lt% inches on the v

(@ (.O .

startu -

_ ~0 percent on ope tg _e if all four RC Pumps (re ). If any feed A r s tions are in Hand, huali ntrol feedwate .'. h maintain the appropriate v

( st generator level

! NOTE: If main e s not available, ver emergency !

! feed wa s start; verify d db(ary pressure  !

! develc(,tQ 010 psig; verif N op4nerator  !

! level spicaned above, and 'a ehergency feed  !

! wat .

-powontheconsolei i .  !

3.0 Follow-Up Actio J The objective V 51 procedure is to conse~se RCS inventory to offset shrink, ensure the core is I percent shutdown, remove decay heat thru the steam generators and arrive at a stable hot shutdown condition.

1.0 FOR UFC IN U \iiT i ONLY

FOR USE IN UNIT I ON _Y 1202 4 Revision 20

1. Reverify the parameter in the steps, marked with an asterisk in Imreciate Manual Action using alternate indication if

- available.

! NOTE: a. If the Reactor trip is coincident with a total  !

! loss of forced reactor coolant 110w, then an Un-  !

! usual Event shall be declared (carry out OPIPf  !

! 1004.1).  !

! b. If the Reactor trip is coincident with t"  !

! loss of the ability to feed OTSGs, then .. 'n  !

! usual Event shall be declared (carry o t  !

! 1004.1).  !

! c. If the Reactor trip is coincide ther  !

! s F, then  !

! reactor an Aler* collant outlet all be temperatur9>t declared (carm' i EMP  !

! 1004.  !

d. ?%

^

! ctor trip is c ' ciden with a  !

! r = +0. 6 ilding pressure > *;cy. then an Alert  !

! e

.e meclared (carry out 'F e 1004.2).  !

! e I :1 ore than one co . I is stuck out of  !

! n 5 g)e folicwing a Rea tp trip, then an Aler  !

! sh ri be ceclared (c4 s u :. PIP 1004.2).  !

! f. If an unplanned EMSMtuation occurs follow-  !

(~  ! ing a Reactor trQ Ufhdual Even shall e de-  !

! clared (carry e P y 004.1).  !

2. Announce the pf tem that the Unit ac' r has tripped.
3. IfpressuriAr n2 drops below 80" 1 .y pressurizer

(

heaterc e .. If not off, p - er control switches to 4

0FF [q ccc e CR.

4 If rg surizer level drops below 40", manually initiate High Pressure Injection. HPI may be throttled when pressurizer level is restored if a SC*F margin from saturation is present and RCS pressure is >1600 psig.

4.0 COH UFC !N UNIT i ONI Y

FOR USE IN UNIT I ONLY u02a Revision 20

5. Verify that turbine bypass control valves are maintaining header pressure at 1010 PSIG.

! CAUTION: Low main steam pressure may indicate the secondary 1 i safety valves have not closed or may be an  !  !

! indication of loss of steam generator level.  ! I i

6. IfRCSpressuredecreasestotheESASactuationidpp ,

(1600 psig), an imediate trip of all reactor )pumpsis recuired. Refer to EP 1202-5, " Loss of Rea r Coolant / Reactor Coolant Pressure."

7. Check for a 50*F margin fro # -ation using the consok rs.

9 NOTE- htNaticnmarginmay'nka[1ydropbelow50*F.  !

! e fy that the m y '. h eturning to 50*F. +

~

S. O n at least a 5

  • from saturation assuring l

adeouate coolin c.. 'e steam generators anc \ reasing makeup.

A ( .

! NOTE: eactor Coolant S 1

t. 'am ches saturation,  !

EP1202-39,"h t Core Cooling".

~ J q

9. Mon '
  • tYe narrow range reactor coolant outlet temperature (Th) on console "CC" to verify that the RCS temperature decreases to approximately 550*F. Verify that the initial pressure decrease is stopped and that pressure begins an increasing trend.

5.0 FOH UFC IN UNIT ONLY

~

FOR.USE lN UNIT I ON _Y . 1202-4 Revision 20

10. Nnitor the wice range RCS pressure indication on console "CC" to verify that RCS pressure remains above 1600 PSIG. Verify

- that tne RCS is within the limits of Figure 1

_11. If RCS pressure or temperature is abnormal, refer to procedures indicated below:

Pressure Temoerature RCS Condition Proceh High High Loss of Feeowater EP "O Loss Inadecuate Cooling #

u a r through OTSG ec. Secondary parameters High Nomal Pressurizer heaters ib off pressurizer on. High Makeup F pa aters. Reduce MU Normal H'a loss of Feef ate EP 1202 Loss Inadecuate g lin3 of Feecwater

/ thrcuch OTS

~ Recheck Secondary

/ System parameters Normal ow in 3 Rec)eckSecondary

\_- Over@gV m parameters Low High A i s Inadecuate ing through W9 Loss of Rx Goolant/Rx OT ' ant Pressure Low Norma,e7 r y 9 stuck open EP 1202 pressurizer sprav Pressurizer System vahe, PORV o Failure EP 1202 Code Safety , lve Loss of Rx Nv LOCA Coolant /Rx Coolant Pressure Low Low Overcooling Recheck Secondary System parameters

12. Verify that the pressurizer code safety valves and RC-RV-2 (PORV) are closed by verifying that the discharge t.p indicators indicate approximately zero, that no flow alarm is indicated on the acoustic monitor for the RC-RV-2 (PORV) and the demand indication for RC-RV-2 (PORV) indicates closed.

6.0 FOR USF IN UNIT ! ONi Y

FOR. USE'IN UNIT I ON _Y o Pei;jonto

13. Energize pressurizer heaters when two out of three pressurizer level instruments as read on RC 1-LR indicate pressurizer

_ level greater than 80".

14 Verify that the pressurizer heaters and spray have returned RCS pressure to normal operating pressure of 2155 PSIG.

15. Recucs pressurizer level setpoint to 100" (25 perceq
16. Verify no substation breakers open, except genera akers.
17. Verify no unplanned or uncontrolled radioact9 ease in progressbycheckingeffluentRMSchannelb
18. Check that a her RMS channels ar N1.
19. Check that \'eM t W Building press . s normal.

9 D

. llowing Reactor 'ild _ isolation valves closed.

_ 20. Verif n

^ (

)_/ ______________ \. ___________________________

! NOT These valves autom 1 lose on reactor trip.  !

( __________ _______________~ __ ___ ._________________________

Q..

RB Sump WDL V534 .hDL_ 535 RC Drain Tank WDG-V~' %

\k WDL-V303 WDL-V304 WD" W }

RCS Sample E)

CA-V1 CA-V3 CA-V2 CA_V13 Rd Purge AH_VlA AH_VIC AH-VlB AH_VlD h.

7.0 FOR U_SF IN U N " ! ONLY

FOR USE IN UNIT I ONLY 1202 4 Revision 20 Core Flood Tank CF-V2A CF-V2B

_ CF-V19A CF-Vl98

__CF-V20A CF-V20S Demin Water CA-V189 (

OTSG Sample CA-V4A CA-V5A CA-V4B CA-V5B Letoown Cooler MU-V3

21. RCS le o or p containment isolation Js secured by reap + \

(r 3 TN,es). This sign (\ p tically resets and allows e alve to be reopen 's a the normal control switch, provided isolation h . so occurred d \ high pressure injection, high or a 4 PSIG b- d olation signal. Ver' y *F margin from at r n anu reopen MU-V3 us 'n thnormalcontrolswit 'so establish letdown flow u urizer level co ol. Observe the letdown ra c io itor for any possi increase.

22. Run rea tivity balance to determine shutdown margin using OP 1103-15 Reactivity Balance Calculation. If reactor is not shutdown by MORE than 1 percent, bcron should be added to the RCS and review event for reportability per AP 1044.
23. Determine the cause of the Reactor Trip. Evaluate to determine if reference to other Emergency or Abnormal Procedures is required.

t 8.0 F03 'dSF IN LLNITRMi V

FOR.USE IN' UNIT I ON _Y x202a Revisien 20

24. Take hand control of the turbine bypass valves, reset the reactor trip and proceed to Hot Shutdown per 1102-10, Plant

- Shutdown. When turbine header pressure is at 895 PSIG, place the turbine bypass valve control in AUTO.

NOTE: Difficulty in maintaining adecuate OTSG pressu ay  :

! indicate a stuck open Turbine Byoass Valve. .

occurs, take local / manual control of the val e

  • lose

! it.  !

0

25. If for some re son the reactor trip ot b reset the following g -a isolated by rea-tor t containment isola O ga- e manual reset: D k a ' 'sy a ves Closed

.. . Sump -

WDL-V534, 535 RC Drain Tank WDG-V3, 4, WDL-V303, RCS Sample CA-V1, 3 3 5 .

R.B.Pury AH-t ,B, ,D Demin ah A- ^

OT ^ C?. 4A, 48, 5A, SB nk wr-V2A, B Sample and N Fill CF-V19A, B 2

Lines CF-V20A, B

26. Containment isolation valves may be opened to obtain samples in accordance with approved procedures. The isolation valves shall be reclosed after.the sample is obtained. ~

f

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9.0 FOR USF IN UNIT ! ONLY .

F.OR USE IN UNIT I ONLY gg;;oo20

27. Other containment isolation valves automatically closed shall remain closed until the following conoitions are met.

_ a. Reactor building pressure is less than 2 psig.

b. Containment radiaion levels have been assessed based on radiation monitor readings or samples,
c. The integrity of the system outside the reac iding has been assessed. (Stable surge tank leve inspection or pressure test should be ct si ned to verify integrity).
d. The Shi pervisor or Emergen ector shall give permi ~Ti'f re-open contai o. + iso ation valves.

D

e. d radiation moni rs ortable monitors shall b lable to detec' =. e ease that may result from opening the valve
28. When the need to op .' is identified - conditions of ,,

step 25 or 26 a- g o oain shift sup 'isor p ...ission, and (l )

bypass the c p containment i o at r as follows:

a. At o- _ Center bypass tne %' .mation by pressing

(

.. hr RS Isolation D , at h buttons RT-1 A, 2A and l

l l A.

10.0 FO;; USF IN UNIT i ONLY

FOR. USE IN' UNIT I ON _Y ng;joo20

27. Other containment isolation valves automatically closed shall remain closed until the following conditions are met.

_ a. Reactor building pressure is less than 2 psig,

b. Containment radiaion levels have been assessed based on radiation monitor readings or samples.
c. lne ir.tegrity of the system outside the reac iding has been assessed. (Stable surge tank leve inspection or pressure test should be si ried to verify integrity).
d. The Shi rvisororEmergeng ector shall give permi 1 'Td' re-open contai .. . iso ation valves.
e. '

d radiation moni rs ( ortable monitors shall b hilabletodetec+ n e ease that may result from

( opening the valv Q.

28. When the need to op is identified conditions of step 25 or 26 a* *o ain shift sup isor p .ission, and bypass the c (k /

p containment i o 4t as follows:

a. At o _ Center bypass the " '

soation by pressing tie-%hr RB Isolation D . at h buttons RT-l A, 2A and k

10.0 FOR USF IN UNIT I ONLY

1202-4 i FO T USE N U N IT I"67LY------ -

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FOR-USE IN UNIT I ONLY 1202 4  !

Revision 20 j

b. At Console Right bypass the "B" actuation by pressing the three RB Isolation Defeat push buttons RT-1B, 28 and 38.

! NOTE: This will allow reopening of valves using normal control !

! switches provided that isolation has not also occurred !

! due to high pressure injection, high radiation  !

! or a PSIG Reactor Building isolation signals. These  !

! valves n'ay be reopened as necesary for plant /h  !

! evolutions after verifying that no radioactiv N N,  !

! caseous or licuid release to the Reactor Bui 4

! has occurred or that radiation levels are c tiple.  !

29. Notify Shift Foreman / Shift Supervisor to h nd submit a reactor trio rt.

s n

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%y 11.0 l

FOR !JSF l\ UNIT i ONi Y

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