ML20085A579

Rev 2 to Emergency Procedure EP 1202-6, Loss of Reactor Coolant/Reactor Coolant Pressure

ML20085A579
Person / Time
Site:	Crane
Issue date:	06/04/1975
From:	Colitz J GENERAL PUBLIC UTILITIES CORP.
To:
References
TASK-*, TASK-GB EP-1202-6, GPU-0500, GPU-500, NUDOCS 8307060576
Download: ML20085A579 (19)

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THREE

?.* LE ISL A*eD twCLE AR STATION l

UNIT #1 D EP.3ET.CY P.0C~M.E 1272-6 LOSS OF REAC70R CG3#.7/F.EAC7CR 60'sLt.*;T PRESS'. IRE Tab!: of Effective Pays Pa;e Dre Revision Pace Da:e Revision Paoe Date R =visc l

1.0 3/13/74 1

26.0 51.0 2.0 3/13/74 1

27.0 52.0 3.0 10/20/73 0

28.0 53.0 4.0 3/13/74 1

29.0 54.0 5.0 6/03/75 2

30.0 ;

55.0 6.0 3/13/74 1

31.0 56.0 7.0 3/13/74.

1 32.0

• 57.0 8.0 6/09/75 2

33.0 58.0 9.0 3/13/74 1

34.0 59.0 10.0 3/13/74 1

35.'0 60.0 11'.0 3/13/74 1

36.0 61.0 12.0 6/CP/75 2

37.0 62.0 13.0 6/09/75 2

38.0 63.0 14.0 39.0 64.0 15.0 40.0 65.0 16.0 41.0 66.0 17.0 42.0 67.0 18.0 43.0 68.0 19.0 44.0 69.0 20.0 45.0 70.0 21.0 46.0 71.0 22.0 47.0 72.0 23.0 48.0 73.0 24.0 49.0 74.0 25.0 50.0 75.0 Unit 1 Staff R me s oval Unit 2 Staff Rec mIndsI pproval Approval I

Approval Date CcapantlkptgHeadl_ Date Cogrjkanyeft.Hp Unit 1 PORC Recommends Approval Unit 2 PORC R? mmerds Appro'ai b'

Mk.. b Oate / /

'75

Date Cts :nas of PORC Chainm, c' PO R C PORC comments of -

included PORC comment: of studed (date)

(date)

/

BY

- Dat e --- --

By-Date 6

• i i

Approval '

• 1' 0 l'W&e e

-3

cas, c.'

<r-7 r St%onsuperintendent/

Unit Superintendent -

m 554 17e i

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5. --- _ 7

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'. J 1202-6

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3/*2.c:

Resisf:r. ;

TliREE MILE ISLA?O h; CLEAR STATI0's uni ( 1 D'.ERGE!.0Y PROCEC'SE 1202-6 Loss of Reactor Coolant / R.C.S. Pressure A.

Leak or Ruoture Within Cacability of Syste, 0:eration 6.1 Syeptoms 1.

Initial loss of reactor coolant pressure & decrease in pressurizer level becoming stable after short period of time.

2.

Possible reactor building h"igh radiation and/or temp. alam.

3.

Possible reactor building sump high level alam.

4.

Make-up tank level decreasing.

i'OTE: The oper4 tor e.sy distinguish between a loss of coolant inside f

.i containment, an OTSG tube rupture nd a steam line break by the followir.g symptoms which are unique to the aforecentioned accidents.

1.

Loss of coolant inside Rx 81dg - RMA-2 particulate, fodine &

.,g, Noble gas monitor alam.

2.

OTSG tube rupture - R %-5 Noble gas monitor alam.

3.

Steam break inside Rx 81dg - low condensate storage tank level alam - and or low hot well level alam l

6.2 Isrnediate Action A.

Automatic Action:

1.

MJ-V17 will open to compensate for reduced pressurized level.

2.

Additional pressurizer heaters will come on to compensate for. reduced reactor coolant pressure.

8.

Manuil. Action 1.

Verify MWV17 open and pressurizer heaters on.

' Rev..

O e

1.0 4

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E

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1

, i 1202-6 3/13/74 F.e.isier. 1

)

2.

Close MJ-Y3. letdown isolation salve. & start additice.a1 f

MJ pu=p (nc-= ally.*.J-PIA)

Rev. 1 Reduce l'oad at 10:/ minute a proceed witn ror=al shutd:wn.

3.

4.

Line up a waste transfer pump to the *S* R. C. Bleed Tank

& pump to the makeup tank to r.afntain rem: fred level.

S.

If for any r*ason, the coerator caa..:

= air.tain rahe-un tank and press:;rfrer leve'Is above their res:ettive low level alam setpoints. trio the reacter, fr.itiate hi cressure in'e: tion Rev I nanually. & then 'close MJ-V12.

6.3 Follow Up Action (Leak within syster.: capability)

A.

Hi Pressure Infection Not Initiated 1.

Initiate plant shutdown & cooldown per 0P-1102-10.

B.

Hi Pressure Infection Manually Initiated 1.

Verify that the makeup pumps & de:ay heat removal pucps start sa tisfactorily.

2.

Bypass the E.S. signal, & throttle MJ-V167VB/C/D as tw:essary to maintain 220* pressurizer level and r.ot exceed 250 GPM/HPI flow leg.

Rev. 1 3.

When MJ purp ficw drops below 80 GPM, as a result of throttling HU-V16A/B/C/D open MJ-V36&37 to previde MJ pep re:freulation path to MJ tank.

NOTE: RCS Loop A MJ pump flow isthe se of MJ23 FE152.

RCS Loop B MJ pmp ficw is the sua of."J23 FE3&4 2.0 O

M 9

9 h

NO]

~

~

1.

1201-6 i

10/20.*~3 li 1,vis :: 0 4.

Verify that the fcilevi=g E.S..equipce=c is in its E S. positice (on panel PCO Actuatio A flef t)

Act:stie= 3 S*Atus P. ! -h Q,,,

Status Light Descriptica Light Sta us S.atus Light'Descriptien I.ight Color Color I

A. E'4ST. SL*P 2C~E-14A

'31oe

' A.! LTT S P 2C-VlJ.3

&loe

3. R.3. StxP IE-Tit 31oe

3. 1.3. SCe DE-Y63 11oe d

C. DE to 2C DE-Y7A Slee C.I CE to 2C DE-T73 31==

D. Diesel A h a4:

31ae D. Diesel 3. on-h 31oe E. Aux. 314g. 2tCC A &kr.

31me E. A=x. 31d. 2tCC 3 Ekr.

Blue 3

T. Scrn. House 2CC A Skr.

.Eloe F. Scra. Bouse 2CC 3 Skr.

31ce C. LPI Line DE-Y4A C.A PI thae DE-T43 31=e L

Sloe H. EVST SCP DE-Y3A i

Slee

.E..EEST scP DE-TSB I. R.B.C. Pu=p A EZ-PlA l

Elue I =!ae J.i I. E.3.C. Pu=p B EX-PIB Eloe J. R3C PP RIC El% 10.1

~

A Nr

• R3 P? REC El-TIC 3

- A=6er K. R3 Tan A AE-Eli I Slse K. E3 Tan 3 AH-E1B

)

,51oe L. RB Tan 2CR ES-T3 A

, slue L.L13 FN 3C15S-T523 Slee M. R3 Tan 2C155-Y33A 313e M. 33 T5 2C1 SS-Y333 Else N. DR Pu=p A :E-PIA

'11==

1 5.aDR Pu=p B DR P13

0. DR TxP DIS Dim *'lA h

Blue 313e 0.*D1 FYJ DIS DI-T13 Blue P. KR PMP A/B KE-P11/3

3!3e F.,5R Py2 B/C KK-P13/C

-Eine l

Q. NR PXP DIS KI-TLV3 Eine Q.;lKI ??? DlS NR-Y13/C h

f

, Blue R. D.C. Pu=p A IC-72A

11=e R.jD.C. Pu=p 3 DC-Pl3 31oe 1

1 I

S. Ns Px? A/3 sS-7:.t/s

,3 se

15. p:S PxP s/C ss-Pls/C i31oe 3

.nL t

i

' 40']

L,=

i

m-1 1202-6 3/1'/71 J

Revis*:: 1 T. NS Deicing NR-Y4A

• Blue T. NS Deicing 27.-V45 51:e U. Aux. BL' Fan AH-E-15A Blue C. Aux. BL Tan AH-E-155 51=e i

I V. SCR HS Fan AH-E-27A Blue V.*SCR ES Fan AH-E-273 31=e W. H-P Recire. MU-V36 Blue

• 4. E-P Recire..T -737 Bise Actuation A or B (Center)

S tatus Status Light Description Light Color d

A. Non ESS. Dump NS-V32 Blue B. k3 Tan C AH-EIC Blue C. R3 FN MTR NS-V52C Blue D.gRB FN MTR NS-V53C Blue 3.

Upon a Borated Water Storage Tank-Lo-Lo alarn of 36", shif-suction of Hi pressure injection from the Borated k*ater 5:.:= age Tank to the Reactor Building Sump by opening DE-V7A & 73, DB-V6A & 63 and closing DE-VSA and 55.

Injection fle.t pac!h is now as follows: Spilled coolant to R.E. sump, R.B. stanqp to LP1 pumps, LPI pumps to MU pumps,.W pu=ps to RCS via ken

---

o-HU-v 16A,B,C,D.

NOTE: Trip reactor coolant pu=ps before R.C. press. decreases below pump NPSH. (300 psig) 1 e

l 4

ew?

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i 1202-6 C 5,'

.-/ 7 5 Reefsien 2 6.

Af ter R.C.S. :n essere de:reases to = 200 psig. theottle HPI

'discharse fitw cy tnrottling MJ-Y:6A/3/C/D. CLserve that LPI ptr ps ro. seliver water to P.CS.via Off-V*A/S.

7.

When KJ-Yl% 52C./D (H21 ficw valves) are closed, stop the Hf pressure in ie: ion pu: ps & close Dil-Y7A & 75 from the LPI pu::p discnarge. Injection flow path is new as follows:

spill cxdiant to R3 su p, R3.sur:p to LPI pty ps, LPI pums o RCS via DH-V4A/B.

5.

Throttle DN/~A & 43 as required to caintain 220" pressurizer level ard cax.. iPI pu=p 'lew of <.3500 gpm. & when tice permits, f

throttle canumG valves DH-VigA & 193 and reopen DH-V4A & 48.

Within about.74 hours8.564815e-4 days <br />0.0206 hours <br />1.223545e-4 weeks <br />2.8157e-5 months <br />, establish a long-term cooiing circu-lation ecde as described in OP #1104-4 and listed below.

Mode T - Forced cire) latien.using decay Heat drop 1Tne.

Mode Z Gravity draining reactor coolant hot leg to the Reactor Buf1 ding sump via the D.H. drop line.

Mode I - Hot leg injection using Pressurizer 1

Auxiliary Spray Line.

Mode &

Reverse flow through the Decay Heat

~

Drop line into "B" Reactor Coolant Loop Hot Leg.

9.

Evaluate raafelon levels & initiate action for Site Emergency as outlined. iin.he TMI radiation emergency plan.

C.

Reactor Buildinc.~rrolation initiated 1.

Refer to sec= ion 6.2 & cc=plete all steps.

5.0 Y

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1202-6 3/12 --

l Resis':.'. 1 1

B.

Leak or ruo<.::m & Sicnificar.t Size So:h Tr.a: vi Pressure 'n!es: W Is AutWticany '. Initiated 6.1 Sy:r.ptoms 1.

Rapid c:antinuing decrease of reactor coolant pressure.

(A) Ls 21am 2055 psig (B) Ls. ' o alam 1600 psig (cogater)

(C)' E.5 actuation alam 1500 psig 2.

Rapid c:entinuing decrease of pressurizer level.

(A) La alam 200" (B) La,-i!.o alam 80" (Interlock heater shutoff) 3.

H1 rae?.ation alain in reactor butiding.

4.

React:pr. building /c:bfent Ter.:p. Recorder indicating atcve norral.

(5G F - 150'F Range)

S

~

5.'

Hi resc:: tor butiding swap level.

6.

Hi. reactor building pressure (R.C.S. er, main steam ifr.e rupture.)

r 7.

Rapid'y slecreasing cake-up tank level.

8.

Both c:nre flood tanks levels & pres:ures are decreasing.

NOTE: Tne serator may distinguish between a loss of ecolant inside containmen:t,, an OTSG tube rupture and a steam line break ty the following; sy::sters which are unique to the aforementioned accidents.

1.

Lost af roolant inside Rx Bldg. - F:G2 particulate, fodine &

Rev.-

Noble. gas mnitor alarm.

2.

OTSG :::ce rupture - PMS Noble gas conitor alarm.

l l

3.

Steam Break inside Rx Sidg. - low ccr.densate storage tar.2 level alam - ana: sr low hot well level alam.

6.0 j

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.l.

I 1202 4 3/12/74 j

Revision 1 6.2 Ic-_ed ia t e ac t ion A.

Autoa tic Action 1.

Reactor grip 1800 psig 2.

Turbine trip 3.

Ei pressure & low pressure injection initiated G 1500 psig,

,500 psig R.C.S. pressure or 4 psis reactor building pressure.

4.

Loth core ficod tank levels & pressures may decrease depending upcn rupture size and k.C.S. pressure. (< 600 psig)

.s 5.

Reactor building isolation & esergency cooling initiated.

(R.R. press. > 4 psig) 6.

Reactor building pressure recorder transfer to vide range transmitter.

7.

Reactor building spray if f 30 psig.

B.

Manual Action 1.

Close.W-V12 (stop, valve on discharge line fron r.akeup tank).

2[ Verify Hi pressure injection is operating properly as evidenced by injection flow in all four 1 cgs. (MU-vi6A/3/C/D)

,he,d Flav indicated on.T23 FII,2,3,4.

l 3.

Trip reactor coolant pu=ps before reachinZ 300 psig &

i verify reactor building cooling and isolition is cperating proper.ly.

6.3 Follow I'p Acties (Lcrge Break - EFI auto initiated) 1.

Verify that all E.S. equipnent is in its E.S. position, by observing that all equipner.t status lights indicate blue with the follo.-ing exceptions:

7 t

I lI l

-Q

4. N 7 l

1202-6 C f *.s, 3 Reeisten 2 (On panel PCP. top center) a.

8KR-G1-02 b.

IKR-G11-02 c.

STM GM A MS-V1A' d.

STM GM A MS-V1B e.

STM G'i B MS-Vic f.

STM G4 8 MS-VID 4

g.

C.F. Tank A CF-VIA h.

C.F. Tank B CF-V1B a

• i.

RSS Pump A BS-P1A

• j.

RBS Pump 8 BS-PIB k.

MU-Y20

• Punp starts when R3 pressure y,30 psig. RSS pumps discharge valves BS-V1A/B open at RS pressure of 4 psig.

NOTE: Should any component not cperate properly, attempt to j

actuate it at its remote switch in the Control Roca. If it still does not operate & the component has a local "69" bypass switch, place switch from "norcal" to " bypass" &

again attacpt to start.

2.

Hott'y Shift Foreman, who notifies all Station personnel over the cross-tied PA system that an apparent major accident has occurred.

3.

O to 20 or 30 minutes past LOCA: Control Room duty operator continuously monitors the following:

a.

Liquid levels in the: (1) Borated Water Storage Tank (OH-TI) OR-3-LI 1/2 8.0

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Revision 1 (2) 5:di.m Thiesulfa:e Ta :k f

9 (ES-TI) BS-3-LI (3) Sodir: Hyd oxide Tank (SS-T2)35-5-L!

b.

Safeguards injection flow rate in each of the's (1) Two low pressure (Decay Heat) injection Ifnes.

(2) Four high pressure (P.akeup) injection lines,

~

MU-23-FI 1, 2, 3. 'and 4. -

(3) Two reactor b 11 ding spray injection Ifnes, 85-1-FI 1 and 2 e

(4) Three (each) reactor building emergency cooling water f.

inlet and outlet lines NS-20, 21 and 22-FI and NS-23, 24 and 25-FI, respectively.

c.

Reactor Buf1 ding environwntal indications:

(1) Sep liquid level (2) Teciperature (3) Pressure

~

4.

Defeat any two channels r' reactor building isolation, then bypass all three Hi pressure and low pressure injection channels.

5.

Throttle as required to prevent pump runout:

a.

Hf press. inj. flow (MU-V16A/8/C/D) 0-250 GPM/ LEG CAUTION: When MU pump flow drops below 80GPM l.

as a result of throttle MU-V16A/8/C/0, open MU-Y36137 to provide MU pump re-circulation path to PJ tank, i

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1202-6 3/13/74 Revnico *s NOTE: *dith F.U-712 closed & rake up pu ps recirculatir.g tnru PJ-35537. event-vally the :.ake up tank relief valve will lift. but the c.ake up system will not be over pressurized.

b.

Lo Press. Inj. Flow (DH-V4A/B) 2800-3500 G?"/:vp c.

Building spray flow (BS-VIA/B).

1500-1800 G:v./ M NOTE: Hi flow alar:5s shculd actuate as a warning to throttle flas.

CAUTIO.1: Should flow in either decay heat line decrease and reai:i I

below 1500 GPM.' complete step #6 below, if not proceed to i a

step 97.

6.

If there is less than 1500 spo flow in one of the Decay H2at (.".R}

1p,,

injection lines. verify DH-Y4A/B console position indication lip.ts show valves are open.

'I 7.

If DH-VA/B are open and flow is.less than 1500 gpm in one of the Decay Heat Injection Lines, proceed a's follows:

Obtain the ad:inistrative keys for the DH cross-connect a.

isolation valves (Dif-V381 and DH-V388) and the DH infection manual flow control valves (Dh-Y19A and DH-V198) from the shift supervisor, b.

Proceed from the control room to the north end of the auxiliary building at elevation 281'-0".

Run a quick radiation survey for any high radiation " beam:s" c.

in the working area.

d.

Rerave the administrative locks fran the isolation valves in the DH cross-connect line and the DH injection r.anual flew control valves.

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1202-6 3/23f;f.

I I

Revisica 1 e.

Open the DE crcss-te::ectir= isolaties - alve (e.g.

.*u.-V-3*A next to the line havi g the higher flev rate as rapidly as Possible and then to crack cpen the secosa cross-consect isolation valve (e.g. OH-Y-333).

f.

Open the second isolstics valve which was just cracked is step e above in the DE crcss-connect line."

3 While openi=g the second decay heat cross-cc==ect isolacion i

valve, throttle either DS-719A or DH-V193 as repaired to achieve essentially eraal flow rates in both D.E. injection

.a lines.

8. Upon receiving a 3.V.S.T.1.0-1.o level alaru 6 36":

If reactor coolant system is above 200 psig:

a.

1.

Open DH-76A and 63, 7A and 75.

l 2.

Close DE-VSA and 58.

3.

hn the Sodium Hydroxide Tank reaches Icw level, close BS-V2A and 25.

4.

When the pressure decreases belev 200 psig, trip the make up punps and close.W-716A/s/C/3, M:-V-14A/3, and DH-77A13.

b.

If reactor coola=t system is below 200 psig:

1.

Open DE-Y6A and 68 2.

Close DE-TSA and SE and SS-72A and 25.

(

3.

Trip make up pa=ps and caose : ;-V14A and 145, and.T-V 16A/

B/C/ & D.

9.

J_f, building spray pu=ps operate, v1.es the sodiun Thiosulfate f

Tank reaches low level, close ZSV4A & 43.

If building spray Rev.

I pu=ps did not operate, (less than 30 psig R.3. pressure) when k.B. pressure decreases to below 4 psig, close BS-V4A & 45.

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10.

k* hen. tire ;e --its, throttle anaal va!.es 0M.'3; 4 : 33

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ar.d reopen

-Y A and 43.

%ithin 22 hours2.546296e-4 days <br />0.00611 hours <br />3.637566e-5 weeks <br />8.371e-6 months <br />, estaclish one ii of the 1ctr;.cr= coolics circulation redes described in i

OP #1104-4 and listed telcw.

I*

g Mode 1 Fcrced circulation usi.g de ay heat drop

.line.

t

~ Mode 2 Gravity draining reactor coolant hot leg I

3 to the Reactor Esilding surp via the D.H.

drop lir.e.

R:t leg injection u' sing pressuri:er auxiliary Mode 3 spray line.

Mode 4 Reverse fitw through the decay heat drop line into 't." Reactor Coolant Loop Hot leg.

6.4 Lono Tem Actien i

1.

Verify all previous actions and carry out additfor.a1 actions i

i as outlined telow.

y 2.

Evaluate sy ptcc:s and determine if possible the cause of the i

loss of costant.

3.

Secure turtir.e. feed water, and steam systen:s when time pemits.

4.

When the reacter building pressure is redr.ced to = atriospheric.

sonttor for M2 buildup and purge per EP-1202-23.

1 5.

Monitor R.3. Su:p for Ph and add Sodiu:n Hydroxide as required l'

thru the de:ay heat re. oval syste:1.

I 6.

As conditio.s per=it. evaluate plant cor.ditions, and return all 1

non-esser.titi equipoent to its norral line up.

NOTE: f.afer to the f;11: sing i,nstructions and procedures for l

additional inforration as required:

12.0 e

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1202-6 05/i:/75 l.

Revistcr. 2 I

a.

Radiation erersecy, plan site crergen:y in t.'.e energer.cy plan.

b.

OP21101-21 Penetration PressuMz2 tion Fluid Block c.

OP-1104-20

' Control Roon Tower 'tentilation.

d.

OP-1104-19 O

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Proced.:re 7.:-Ser 1207-?

Proced'.. e Ti:le L:ss ?.. C. /.:.:". T. 7-s.< : r e F.cvie.rIn: C.-;s.I:stien

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C=:ren: *e :ep La:e 7-7 0 -t**

Cc.._+. :s,7a 1ved (02:e)

?-12 '-

e l *:C:.::mn:

u O? Pars Co:r v.n t S1..ma: f t

.:-.; rated h T4rsrks Tm?e I

r.e' ete t f.m 3:= ed ia t e gil i.6.7.E.?

Include nstify shift fm T.:s

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Th::* n.

e 1.b.2.3.3 Close TD-V Sta.rt

~=.1 ft.;.h ::;,.

Tes l

1 i

4.G.3.E.?

t 1.

ES St. auld r.ot.be by-passed wh.c: nigh.- s-i o

>,*.-pesinc 11.1 L vec CPerC sure inf ec

Ion begi=s.

!! or t.sar.s of controllin;, D l

. M er Inventory and throt ;

,,.linr. li?/12 pu p to mtinte.

{lcwrates.

j A.G.3.3.?

2.

1:71 r.=2 at full cap.acity when ini ~ ate-1.

h.s lq.in recirculation on iiPi pu ::.s whan approach nIn f;.

.l

,"b. :In:afn ses11 inject on.

-:ri rs[ery stand psInt,

.. 6. 3. is.2 3.

ShutdWn iCI purp vice, opcs r e:ir :Cari.q Es t

i i

line.

e h* -u :s IIvs.vice tf rh. in j '

+ection t'.a u 7 liner..

A.6.3.3.5 L.

Don't cperute dwa;.- beat systen.d.es R.'.7.

ho

). cps 33.as.L and 6 clara.f 1, pressure is groster than 2.W.

,to Indicate u:.o of LPI pu :

lin boo:ter purp rode when i

't"l3 pressure Is greater th

{'

?00).

A.6.3.h.5 2.

Decay 'ricat It p net to exceed 3503 G.F.F..

Ies j.dded precaution to A.6.3.

e cc: r.essrs. J. J. colitz K. A. Creene Reviewing Orgasisation/

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%P2 :- '.-:.: = m1 :: Ion Proced.:: r : -ter 1222-6

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• css ?. 0./P.. .S. Press _ v 1

Proced. e '"I-le 3Eii Reviewi c Orga:Isatio:

t --;,.,tter case 2-26-74 Co.ne=ts 'ies:1ved C.ateh' 3-13-74 I

Co-rns:

I Pe= arks OP Para Conwr.: S m Ince c: ste:1 Yes..~o s

Yes uded' p wcautico to A.L.2.

A.6.2.B.1

. Note that ES-V-1A/3 spray pu=p discharse valve open at 4f.

7 S.6.2.B.2 Shift foreman actif ation & asno.= :e=e..: ci Yes

ncluded in s e; 2 follev emergency to be ac==mgelished after EPI now rp action.

. veri"Icstic.n.

e.

I' ti b.6.3.2.

Don't defeat f.S (*t nactor huildi=g signal)

s py-passing reactor buildi:.

f signal I.s =ece::sary to throttle E?/*P 4:*.scharge ralves. - o.ain:ala HP *J nr:p allovable flow rates.

3.6.3.3.A Don't open HPI M.J.ation valves. Step Ee

" rom safety stan! point, 2nd make-up pu=p I= event EPI flow is low due r.aintain s all injection thru 4 li=es with reci.N.

to thm ttling EPI d.ischaz.e valves.

flow vice EFI flow thru 1

nly 2 11ses. NOTE:

H:w-rver that : :cedt:re has wen e.arred to soecify, w i.rc. valres are onil

pened v.e. =ini:-.n ilo e :,

la G.w. :er.r.: pt::p is be '. <

ipproacced.

cc: Messrs. J. J. Colitz L A. Creene Inrisring Organization /

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i 1202-6 Procedure !;u+ter Ioss R.C./R.C.S. Pressure Procedure Title i

Reviewing Cr;;asica:Los 33 2-2674 Co:nent Letter :: ate 3-13-7" Coenents 74 solved (::atel

- Coment l

Inceyrated P4.Mks OP Para Cocrent Su wry Yes/::o B.6.3.3.C rallure of LPI pu=p will cause,:ero LPI flow Yes

. Deleted reference to indication. Not 1500 GPM.

diesel 5 decay heat pe.p failure & added step to op decay heat cross connect i JI flow drops to less tha 15n0 (;PM.

+

j ec: Messrs. J. J. Colitz K. A. Creene Reviewing Organization /

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E.*....d 7....C(

THE E!.SCOCK & WILCOX CO?'PANY 5'

F D ' G b" ~' )

P04tR GEi.ERI. TION GROUP'

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itECZWED

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J. D. PHIOT5! - SITE C d'P.'.C"l.3.v.A %~I'3 - 0 0' From

.C. C. SC'.IECE

'"E71 PETTA*' 5".lFER*.*I!CR (2L56) ees. 3.3 Cust.

FiIe No.

USS-5 yr ED 8' E*I*

g Subj.

Date IC7II'J O? O.I-1 PROC Y.;hES FEBRUARY 20, 197L j%.

E=c1: sed are the folleving 00-1 procedures 'which have been reviewed by

clear Service.

CN N [C D Ioss cf EC/3CS Pressure OP-1102 01-Plant Eestup to 525'?

• EP 1202 02 Etstics 2iacko rt & 31sekout h*1th Ioss of Ecth Die:e1 Generatcrs

• CP 1103 02 Fill s.d Vent of RC Systes

. OP 1105 11 Secondary Plar.t and Juriliary Systems - 23I r

SOP 1104 30 Euclear Eervice River Water Systes For 1105 C2 Reacter Protection Systen

'0? 11C6 lie P.ain Etes= System

• EP 1202 29 Pres:.: riser System Failure sCP 1105 09 Cor.tr:1 ?.ci Drive System CN14C311-Draising aci 2 Blanketing of RC Systen 2

Q? 1102 02' Pla t Startup

'ihese have been revieved for istcractice with I.2 su 111cd equipment and sy:tc=s. Cc :=ents reistive to syste= protection or..eferred method of c;erstion have been included. No ec.=ents con =e:ning for..at. gra s ar. super-fluous infor=stica or co.venience hsve been =ade.

Onese reviews reflect currest cperating phil :=phy s.i reg.airc c=ts, but of course, not any conver-saticas or infor=atios pt: sed icfc. ally tetvees 21*/ site personnel and the ca:to=er. Were applier.hle, ca=pliance with 31W da aft procedures has been verified.

!!'/J,y__W..,3 CO.3/hh a

h elocures I

c::

R. R. Beach E. E. Suhrte V. S. Delicate i

8 l

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Co=.e=ts cc F.=erGency Proce' dure 12C2-6, Ios: of R.*/?C' Pre.ssure

'Ihree !!1le Island - L* cit 1 A.6.2.P.2 - I= mediate action should pretably not include =ctification of the shift forec.as. Ihis should be done as c=e of the fir-t fc11cwp a: tion iter.s.

A.6.2.B.? - Also close sesl return isolation vs1re. 'C-V25. TJ-Pla is not nece:sarily the ;u=p which vill be startei at this ti=e, this depe.is on pu=p ccaricurstics prier to loss of RC coolast.

A.6.S.?.? - I5 should not be byps.ssed when h?I is b=r.:..

HPr should be ns at full espacity whe initiated. If Icak is withis et.pacity of IT:, the j

valves !.J-716A/3/C/D =ay then be throttled to =sintais pres =url:er level. If l

the ETI required is Icv enough, a pu=p may be shut der. i r:ther then openiss

{

recirculatics 11ses.

A.6. t.3.5. L'ith the exceptics of using the de:rv heat system to supply the s

makeup syste=, the decay heat syste= should not te plseed in opera *. ion above 200 ;sig. Tais protection of the systes is furt?.er ir.sured by DH letdown line (DE-Y1,Y2) interlock which will prevant opening of these valves above E3 syste= design pressure limits. Ah additic=21 precautien that individual DI pu:7s shall not exceed 3500 gys, this is the high flow alarm setpoint.

B.6.2.3.1 - It should be noted here that in addition to starting R3 spray pu=ps

~

ca 2.33 psig R3 press., A separate ES co==:nd opens valves BS-V1A/B to initiate spray. Tais is en i=portast consideratics if E3 spray must be manually a:tusted.

B.6.2.P.2 - sotification of the shift fore =as should be deferred until note 1 :portant i==ediate ite=s (like verification of h? injection operation) have been ec=pleted.

B.6.3.2 - ES should act be defeated while an e=ergency condition exists, this i

should be made clearer as to conditions existing when this step is performed.

l V'

B.6.3 3A - By opening > J-V36, MJ-Y37 95 spa per pu=p is recire21sted. By 1

checking that required minimum flow for pumps is =aistained, this recircula. tion is not needed unless fice is too law. However, a pu=p will be shut down prior to this so 2.ere should be no need to recirculate.

B.6.3.?C - Si=ce decsy hest crossover is located dc. tstress fres f*cv indi:t.ios, the flow.ill not decrease to 1500 sps with the loss of one diesci and the s.sso-clated decay heat pu=p.

The flow indication asso:iated with phis rusp wi1*_.o to rero flow. Beetics 36.3.li vill need to be chc=ged to reflect this fact.

j I

Co=2ests b.

/

c. J.0 :ee?.: & *1!1eox f"uelcar Service 1

l Date: Fet run-- 90. 1"Th i

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