ML19224B230
| ML19224B230 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 06/23/1978 |
| From: | Metropolitan Edison Co |
| To: | Mullinix W NRC/IE |
| References | |
| 2104-1.3, TM-0019, TM-19, NUDOCS 7906140261 | |
| Download: ML19224B230 (41) | |
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2104-1.3
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Revision 11 s
1n;v_ ca t es/23/78 C/ > '
THREE MILE ISLAND NUCLEAR STATION D
U.C 42 CPERATIflG PROCEDURE 2104-1.3 DtliY HEAT REM 0'!AL SYSTEM Table of Effective Pages
??ce Date Revision Pace -
D a t e-Raision Pme Date R evision 1.0 11/07/77 3
26.0 02/27/78 6
2.0 11/0//77 3
27.0 02/27/78 6
1.0 0/ 0 // 73 6
73.0 02/27/73 6
1.0 11/07/77 3
29.0 F0/21/73 6
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Revision 3 11/07/77 m'
THREE MILE ISLA';0 T;UCLEAR STAT 10Tl UNIT #2 OPERATIt:G PROCECURE 2104-1.3 DECAY HEAT REM 0'!AL SYSTEM Table of Contents S ECTIOil PAGE
1.0 REFERENCES
2.0 1.1 Der. ir.gs 1,:piic,51e ice 0,._. a :n.
2.0
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1.0 1.2 1,
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3.0 f - ffgj ' 5 If S_
6.0 a.0 F T.C C E'j R E 9.0 4.1 Startup.
9.0 4.2 M ar r:1 Cpara ti. n "ac Tc ay ::e t t aval.
13.0 4.3 Shu r f or.n.
13.0 4.4 f;:ci al or Inf :g nt C;m tic.s.
15.0 4.d.1 Pl.ic t,ig th; ::i Sjs ta in E r;5 S t.;by.
16.0 4.4.2 LO:.9 tarm circulati;n chs to pr.
- nt Eccon c:.. cntratico 2"fec.s.
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2104-1.3 g
Revisico 3 jj 11/07/77
.L '!
THREE MILE ISLAND NUCl. EAR STATION R23 a UNIT #2 CPERATING PROCEDURE 2104-1.3
~
DECAY HEAT REMOVAL SYSTEM
1.0 REFERENCES
l.1 Drawings Applicable for Operation.
1.1.1 Burns & Roe Flow Diagrams.
1.
Reactor Coolant Make-Up Purification (2024).
2.
Spent Fuel Cooling ind Ncay .u t '- a ll WS),
" ci
.c S-
'l '.g (: Ji 31 ).
3.
',,1,3 i. 9
- j -
'T 1
q.
a a,cr 1
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'rce _
- 14 l.
ciO3-1.4 F.C P'
- Cr c
.an.
2.
2102-3.1 Uiit 9 atdrsn.
3.
?l02-3.2 Unit Ccci?can.
4.
2104-1.2 l'aka-Up and Puriiication.
S.
2104-3.3 Cecay Heat Cicsad Cceling ' iter.
6.
2105-1.3 Safety Features lctuaticn.
7.
2102-3.3 Cecay Mcat Remc.>31 via CSTG.
8.
2202-1.8 Loss of Cecay Heat Ruoval.
9.
2203-1.7 Rive '. ater System Failure.
1.3 Syste:a Descript cns 1.
Cacay Heat Renoval System '.'ndex No. 20) 2.
Decay " eat Closed Cooling ',Jater System (Index :o. 29) 3.
Spent Fuel Pool Cooling Systam (Ind?x ':0. 21) 1.4 Figures h
1.
Maxir"c-mininum RC pressure during simul tar.eous c.:eration of RC pucps and Cecay Heat System, rigure 1,
~
'*dximum-minicu:n RC pressure during operation of DH Sys hp.j tn 2.
no RC urps cperning, Figure 2.
- eq 4,
y,$
ra a ~ ~
2104-1.3 R,visir.n 6 02/2//78 3.
Peactor coolant water level required to avoid vortex formatica and provide the NPSH required for DH pumps, Figure 3.
2.0 LIMITS AND PRECAl;TIONS 2.1 Equipment 1.
Do not exceed a maximum DH Pump bearing temperature of 180 F.
(Cc..putar points 336, 333 for CH-P-1A and 337, 333 for CH -P-13).
P.
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ala
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i 1,
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r r.nts iCi6 Tur CE-P-1.1
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7 T:e "!-?-13).
5.
Do 'u t < r ed 2 L _ccss;<? D. H. w c ur > irts.
i > : '; ;
mt i.
cris tar t i s allc.
,d a f tar t':e.ator sti'.ar '
_- :ur3 drops Leicw 3"C of the nocol ce : ting t= par.'.re.
6.
Ensurn at the "
- i run ail: :able \\T of
?O'? b., '
in D.H.
' n e. -
i :d.
(!
p "n"
- Ti T !1,
,: u c i a r i t.5 2 ar.d sh211 DC-TI-957, Loop "B" - ?!- 5 -T2,
~:C-i!- 0C8, l ec i tu J.;n P' ; 21 53).
7.
Ensure that the.raxinum allowable flou per D.H. cooler of 3750 GPM is not 'xceeded, (CHI-FI1,2, lccated on Panel #3).
8.
Before initiating cooling 13ter flou on ei ther side of D.H.
coolers ensure that the ccolers and all conr.ecting piping is filled and /entrd.
9.
hen chrnging ficw on eiSer side of tha D.H. coolers ensure
_j that the raxir ;n 211c'..able cooler flo.i (3/E0 G7:1) is not dKd0ded.
3.0 9 ! O h6 4h e o.k d I N dhN 3
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2104-1.3 r.evision 3 s;
11/07//7 10.
Ensure that the flush watcc supply to the decay heat pu:q.
mechanical seal does not exceed 500 PSIG as read on PI 464 &
466 located on Panel #8,. (Computer points 115 & 116).
11.
Ensure that the return pressure from the c.echanical seal cyclone separator does not exceed 200 PSIG.
Since the seal ter is roture.ed to t' e Cccay "a t t .z/al P '? Sucticn 'his f
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we 12,i t
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.n. ! )-ill ad 2 on ccolant s;:t ' - ' ' '
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,I 0 t tha tu cra ture l ' i t o f
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.~ ; 21
.ni' s is r.a t <
.C dd J a d.
13.
':han t'.e.% 3c tor C al.a t Sys te., h a s 5 :n ', r 6.n
.d
':,: s s u r ued '
i sol a te the Bor 'd '.' Iter < ta r g e i a n
- r
- ., the 0 9 ccy "u t f
i
' ' c. : s c i a c e ' 'n e Ejs t em by ct.e c '. ng,1 c.c e d Ch...,
id 63.
sodium hydroide s'arage tank fe;, the Cch limt 3: 7nl i
I System by chect;ing closed D !-VSA and 38.
2.2 Administrative 1.
Do not operate CH pumps in the recirculat:cn mode for are than 10 minutes without ccoling..ater cut in to coolers.
2.
Should pur.? cavitation occur or if a high fic alarn annuciates (3750 GPri) throttle deccy heat cooler discharge valves DHV-128 f./ B.
a 3.
The D.H. System shall be isolated frca the RC systen.. hen RC 2
pr:ssure and tenperature is greater then that shci,n n Figures 1'
1 and 2.
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kI. h.l pgd. :i yt\\t%.-
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2104-1.3
'h Revision 8 04/18/78 4.
Ensure that RCS pressure 's maintained above that shown on Figure 2 to prevent the for.Tation of a steam bubble at the highest point of the 36" reactor coolant piping.
5.
When operating the decay heat system simultaneousiy with the RC pumps ensure that the mximum RC pressure for various PC pu p cc-binations is not 3.s c c e !ed.
0,efer to Figure 1.
6.
m., ca '. a g ' M >'
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- e, or SF in ny 1/.' lwr per <i, is ot w.
d.
8.
'!a r i fy.' a t.J-Vl 9, 3, C, 3 >.' cl. W.ti "nr
+. Je 5ccih es m:n prior to ?l'.;;r; t.e C.ay ' it Syst: 1 in cperation to pra.:nt c.erpre:ari:2;ica f
- s. : 0 - :ay . 2 t Sy > t a r. I n ' :.e
' vent vf cn ida :r :nr
- 3t"n of E.S.
9.
-i ~y '.a t CF-il A, 3 cre :
_ :o md thei r r=s pec t. ca be:J,a rs are cpsn prior to placing t".e Oc :n Hcat S stem in c,.mcon 3
to pre sent c'.erpressari:2tica of t:;e Cecay :.e3t System.
10.
Folic. ting system Cooldcwn, the R.C. Syster will be E:-cpl ad a t the Cecay Hnt Cooler Discharge to assure :nter quality, as specified in the Tech. Specs.
11.
Insure the sodium hydroxide tank temperature is mi:.tdined between 50 F and 120 F as read from parel 8 CH-8-TI.
12.
CAUT I C'i:
Co not open CH-Ji /3 simul taneously with :! '/SA/B
-2 f
drain into the R3 sum;I.93 209 o r t h e ?'..'S T w i l l 13.
Yhen draining the.iCS far 3.CS compcnant capair, insure LM.s fi cw i s thro ttl ed (using 55,'-128.n and/or 3) as Per r i.;u r e
'3 (tha e r 11 310b h.
- n..i s a.is 2104-1.3
.o
('
Revision 3
'/
11/07/77 4 to prevent vortex forr.ation ar.d possible loss of suct. ion to the CHR pumps NOTE:
This is to prevent the accidental flooding of the R.C. System during component maintenance when R.C.
System level is reduced.
14.
hen the DHR System is in aparation, without any RCP's operating, in licMei DH return tc gerc '_ ara (E"2-TI-l '.2
.i ?'. 31 1) -hall
'o 41 is t b 2CS '
- 1. '.,
2
.a s.
i s
c,-
se 16.
" o nf.cnince si:all be all d ac, d
- : r ' ; c '_,
.3
- n.ny
- c. menents in the !ecay heat sjste
.iich.ill at i sce th.n cne cecay h 'a t ' rain fec a ser, ice.
Cc
- ds shall not be r ccved fre' vic nch
.at t':e a f fx t ui afstc.r. 'nin is irgerable for..:re than 72 c m uu ti ze '.ars. I f :he j s t.:.a is r.ot rastered.ithin 72
- rs *Ee r
- =t: c : hil ta p'v 2d in a nat shutic..n cardition.,ithin 12 hc_rs.
17.
'. Rile operating in the E.S. c.ie
- sure
.'at..dn the T..ST Icw-lcw levei alerm annunciates, (approx. 7 ft. from bottom of tank), the decay heat pu.mp sucticn aut:matically shif ts fecm the B'.!ST to the RS sump by the opening of CH '!SA/S.
Whan CH-
'!6A/S are full cpen, CLOSE CH '!SA/3.
Failure to transfer sucticn will result in loss of ECC injection.
3.0 PREREqt'; SITES (Indicate satisfactory completion by Initialing each step) e
APR 2 3 $I3 -'
2104-1.3
~v Revision 11 0
C5/23/78 3.1 The Reactor Coolant System is cooled dc'.sn to aoproximately 250 F and depressurized to <320 PSIG.
3.2 The decay heat ;losed cooling water system is operating per
. operating procedure 2104-3.3 (DC '!8A/B, Inlet valves to the decay heat raraval coolers are open and DC '!73A(3) is throttled to ma in tain r.. n ina fi ca '_'
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3.3
.:r is ' mil nle at the
... d ;.:e l-2d ':e!..e:
1.
- 160'!
ru i m :r :d s a f e t1-T., ; '. u r a s :' : s 2 - l E.
(1) Uni t l E9 - Cecay 1::a t P" : /11 ?.
p (D:1-Pl A).
i 2.
il 5C'! - %g i'. er 2d s a f ty f.'. '.r 's 5us 2-2E (1) UniF 2 Ell re.ay "'at ' aval ~, (S"-P13) 3.4
~.er is mil Bla at the ~otar c;' trol c.ter; l'.3 t zd ';al.
n.d associa tad breat,ers arn closed.
1.
120'! - Er.g. s2fety system val es c:CC 2-liEA.
E.S. '!alves :'ator Control Center (1)
Unit 8CF - CH '!4A - Decay Heat Discharge Isolation at Cantairment '!assel.
(2) Uni t 3DR - C:1 '!EA - Cecay :': eat Suction from E'. 3T.
(3) Unit l AF - CH '!6A - R.B. Samp tc.irculaticn Suction.
(4) Unit ICF rH '!7A - D.H. Heat Exchanger Discharge to ::V pumps.
(5)
Unit 4A - DH-C Ecdium Hydroxide Storage Tank ":2 tf 8)j c 1 l q
(6)
Unit 2DR - DH '!SA - Sodium Hydroxide Tank Discharge
'!a l u e s.
(y
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gp J.o d t M id
- p N%A!ki
2104-1.
G23W Revision 11
/
C6/23/78 (7)
Unit 6CR - CH-V3 - Primary Loop to Decay Heat Pumps.
(8)
Unit 13CR - CH-VIC0A - Decay Heat Pump suction cross connect.
~
(9)
Unit 10BR - DH-V102A - Decay Heat Removal Pump CH-P-l A suction _
(10) Unit 148R - CH-V12SA - Decay Heat '#r : val Cooler DH-C-1 A Discharce.
2.
- 37 - Eng. Fafety Eyst;
- 1 /il.cs 'CC2-?l'A (i)
U., i t :CF - CH/!'3
^ my lt P P arge I. ;ia tico a t Cccit 2;... n t V ~ _ 31.
(2)
Unit 23R - EM-V33 - Dec2y " eat Soc i:n fc_ a _ !ST.
r (3) Unit AAF - DH-753 - R.B.
S-.,p Recirc.ula; an %ction.
(4) Unit 73R - CH-V73 - D.H. :: cat Exchinger DisrSrge to MU Fumps t
(S)
Unit 13CR - EWST " niters DH-C-1 45R Ch-7 33.
(5)
Unit 433-CH-V33 - Sadium Hj.irnida T.nk I::? ition Valve.
(7)
Uni t 7CF - CH-V2 - i'r. ury L ;cp to Cecay Hca t Pu.:.ps.
(3)
Unit 10AF - DH-VlC03 - Cecay Heat ? ump suction cross connect.
(9)
Unit 113R - DH-V1023 - Decay Hea r Pump OH-P-13 suction.
(10)
Unit 153R - CH-V12E3 - Ce:ay Heat Remaval Cooler CH-C-13 Discharge.
3.
430V 2-323 - Valve E'otor Control Center.
(1)
Unit 2AF - DH-V157 - E'.!ST to SF Cooling System.
(2)
Unit 2CF - CH '/193A - Decay Heat Ccaler Discharge Cross-
-j Connect.
4.
430V 2-423 - Valve Fotor Ccntrol Center Unit 2DR - CH-Vl933 - Cecay Heat Cccler Discharge Cro/ 93
,f 2 (1) ss-t.
connect.
1 i
d W a,t U m m h,4 L
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2104-1.3
.FR 2 3 1973 P.evision 3 J
/ ~'
11/07/77 5.
480V MCC 2-llEB (1) Unit 1BF - DH-V171, Primary Loop to CH Pumps.
(2) Unit 2BF - CH-V1, Primary Loop to CH Pumps.
3.5 Perform valve line-up per Decay Heat System valve line-up Check Sheet Appendix A.
Upon satisfactory completicn sign valve line-up Signature Sheet Ap.:endix B.
3.6_
Cecay Heat Pump centrol s iitches irn i n PULL -TO -LOC K.
3.3 120 ' AC Cable 0:c, C2';i-3 t *:a. 1:3, C.9. I nel ':o. 3 is -
j t..:d and the folicwing Sr l'ser is closed:
3.8.1 Ckt 76 - CH-Vl/171 RCS Pressure inteclock.
_ _ _3. 9 Insure the Ce:3y Heat Wroval Systr is filled and cented.
.0 STMT;_UP PRCrFluRE_ (Indicate satisf ac ;cy ccmoletion by initaling each step).
- 1 31 te RCS
- m; erat tra and, :;c' re 5 in "2 r.:g 2 = 11 :. !;10 for ral ta.ucus operation of batn ti.e RC
. is :,d the &: 2/ mt 2
removal system as per Figure 1, star t :he CHR systcm as fulle.is:
4.1.1 To prevent c'ierprassurization of the CHRS cn an inadvertent initiation of E.S., de-energize LUV-ISA, B, C & D (high Press.
Injection Va'.ves) open the following breakers:
1.
Cn Eng. safety system valves MCC 2-llEA (1) Unit SCR - MU-V16A (2) Unit 90R - i:U-Vl63
?
2.
On Eng. safety sys tem valves *::C 2-21EA 2
(1)
Uni t 90R
,MU-V16C
~
T y
d
MR23 -
210?-1.3 Revision 3 j'/
11/07/77 (2) Unit 10DR - MU-V16D CAUTIO?l:
Insure recirculation path for the Makeup pumps is lined up in accordance 'with " Makeup & Purification" Procedure 2104-1.2.
Read and record RCS wide range Tc as indicated on RC5A-4.1.2 TI-l F and RC53-TI F on control panel #4.
4.1.3 _
C,:en CH '!4A (CH-P! A Disch. Isol. Valve to 7eactor '!..ssel) and CH '!03 (C'i-PIB Disch. Isol. Val ce to bactor '!
sal) freia panel d4 a.1.4__
Open CH-V2L'!3 Decay '!aat Suction isol. lalves frc a Auxilicry Sys'.sas centrol Panal #3.
Cpen CH-V1 (Cecay Heat Suction Isclatien '/alve) fram 4.1. 5. _ ___
Auxiliary systens control Panel #3.
NOTE:
If CH 'll does not open, place the MCC ?-ilE3, CH-Vl/171 Selector Saitch in the CH-Vl71 ??sition and cpen CH-Vi71.
d Close OH-V102As3 (CH-A33 split suction fec7 sodia.a n/ ro.
4.1.6 tk/5'.45T) from Panel #8.
Open DH-V100 A33 (RCS to CH split suctica vai m).
4.1.7 Throttle DC-V73A(B) to minimum flow allowable.
a.l.S CAUTION: Do not exceed a 100 F tercerature change in any 0
one hour period.
From Panel #3 start CH-Pl A(3) at Panel #3.
Check flow on 4.1.9
" A"(3) CH Flow Indicator CH-1-Fil(12) and throttle to E00
_f nd h 193 214 (g !j. $qe$hp!
- pJ
2104-1.h nrit 2 3 t3; Revision 8 /M '
04/18/78 GPM flow with D.H. Cooler "A"(B) outlet throttle valve DH-V125A(B)'. -
4.1.10 Read and record the CH return ternp. to the reactor vessel as indicated by DH2-TI-l and DH2-TI-2 on Panel #8.
C6mpare these temperatures to those recorded in Step 4.1.2.
CAUTION:
Do not exceed a cooldoun rate of 100 F in any one hour, 75 F step ct inge, or 50 F in any 1/P.
hour period.
i;0 T E -
After the C: cay bat Rroval System '
rer;ture as ind:c ite-! by D.!2-TI-l mi 2..n I:nel =3 is cqual to R: 3ctor Ccolant Sys'.em t, tratura as indica ted by RC5 A and B-II-l on Pinel d4, with Cecay :!ea t 0.e.noval System in opera tion ind Reactor Coolant pu,ps operating, trinsfer removal of decay neit frcm the ance through stea.n y:nerator to w e Da.aj Ha t Naval Sys.em, as indica ed in Step 4.1 11.
4.1.11_ _ _
Adjust Decay Ha t Closed Cooling '.hter flow thru the CHR cooler by throttling open DC-V73(B) B from Panel fB (DH ccolers A(B) outlet valves).
At the same time, from Pinel #5, using the ICS hand / auto station for turbine bypass valves (MSV-25A/B & 26 A/B), sicwly close the turbine bypass valves (MSV-2SA/B & 26A/B) to inaintain the RCS terperature at the desired level.
Continue this operation until all bypass salves are closed, as indicated
}
on Panel e5, and decay heat is being reroved by the C3 cay Hea t traaval System.
193 215 J wn uh. ?mWR
2104-1.3 LLJe A?R 2 3 W9 -
Revision 10
.y 05/03/78
/ 9 4.1.12 With both the Decay Heat System and RC pumps running establ'sh cooldown ficw to pressurizer spray line as follows:
1.
Open decay heat 'oop A/B to pressurizer spray line manual isolation valver rH-VIS6 A/B.
Open decay heat to pressurizer spray line common 2.
manual isolation valve CH-V137.
2;0TE:
The decay heat system is now lined up to provide ccoldc..n flow to the preasurizer via RC-V149 per procedure 2103-1.3 " Pressurizer operations" CA'JTIC?lS : CH-V137 is a ranual containment isolation valve.
If a Reactor Building Isolation and cooling signal is received..hile this valve is JFEN: CLOSE DH-V137 a.1.13 When satisfactory reactor coolant pressure control can be maintained by using RC-V149 only, and as directed by the unit coold:'c.n procedure 2102-3.2.
Scura the ;perating RC pungs in accordance with RCP pr:cedure 2103-1.4.
4.1.14 Continue with cooldown, in accordance with procedure 2102-3.2 " Unit Cooldcwn", to the desired RCS temperature as read on CH-6-TI/T2 by throttling CHCCw cooler discharge valve DC-V73A(B) and/or DH ficw control vah e CH-V128A(B).
CAUTION:
Do not exceed a maximum cooldc' n rate of 100 F U
in any one hour period, 75 F step change, or U
50 F in any 1/2 hour period.
-j 193 216 9fM 4 !df!@ 6T[9[d"hm@uin njud A idi jj
! Q-2104-1.3 AFR 2 3 rg3 '-
Revision 10 A/
06/08/78 4.1.15 When the desired RCS temperature is reached and prior to RCS reduction to reactor building pressure, isolate ths' BWST and sodium hydroxide tank from the D.H. system to
~
prevent inadvertant flooding of the RCS by the folic'. sing procedure.
1.
Verify that the requirements for Technical Specification 3.1.2.8 for modes 5 & 6 are met.
The RBAT or BAMT should be used to satisfy T.S. 3.1.2.8 as long as a ma'seup pump is operational.
If using the R3AT the applicable valve lineup is Attachment 23 of 2301-M2.
The applicable valve lineup for the BAMT is Attachment 2A of 2301-M2.
If RCS pressure is 1 150 psig the EWST iny be used to satisfy T.S. 3.1.2.8 and valve lineup Attachraent 3 of 2301-M2 must be completed.
At 5 60 psig RCS pressure, the BWST may remain the T.S.
source, or the EAMT or RSAT may be used and either Attaci.nent 4A o_r_ 4B of 2301-M2 is the applicable valve lineup.
NOTE:
The makeup pumps must not be operational.; hen A or 43 is used.
2.
At the 480V Eng. Safety Features Sus 2-ilEA, open the folle. ting breakers:
a Unit 2DR - DH-V8A (Sod. Hydroxide Tk. Isolation Valve) b.
Unit 3DR - DH-VSA (DH Suction frcm EWST Isol. Valve)
_t I93 217 b
j rl ~ ^ t 3 nr3
, LC-7~
~
2104-1.3 Revision 10 05/C3/78 3.
At the 480V Eng. Safety Features Bus 2-21EA, open the i,-
following breakers:
a.
Unit 48R - CH-V8B (Sod. Hydroxide Tk. isolation valve) b.
Unit 28R - CH-VSB (CH Suction from SWST Isol Valve).
4.2 D4 System Normal Operation for CHR.
4.2.1 The DHR syst;m will be regulated to maintain the desired RCS temperature (as indicated by CH-TI-1(2) on panel #3) for refueling and/or RCS component repair by throttling DC-V73A and/or B or DH-V128A and/or B.
4.2.2 RCS clean-up via the decay heat system can be accomplished in accordance with the spent fuel cooling system procedure 2104-1.5.
Draining and RCS pressure reduction to reactor Bldg.
pressure for head removal and/or RCS component repair will be performed in accordance with operating procedure 2103-1.5 Craining and blanketing fl the RCS.
2 4.3 SHUTDOWN PROCEDURE The shutdown of the decay heat removal system will be accomplished in conjunction with " unit heat-up" procedure 2102-1.1.
3 218 13.1 O
Li-!3 Revision 7,6j is a '
d 3 *ali 03/17/78 At the 480V 211EA E.S. valve motor control center CLOSE the 4.3.1 following breakers:
Unit 2DR CHV-8A, (Sod. Hydroxide Tk. Isolation Valve).
1.
Unit 3DR DHV-5A D.H. (suction from EWST Isolation Valve).
2.
At the 480V 2-21EA E.S. valve motor control center close the 4.3.2 following breakers.
1.
Unit 48R-CHV-88, (Sod. Hydroxide Tk. Isolation Valve).
Unit 3SR CHV-5B (D.H. Suction from EWST Isolation Valve).
2.
In conjunction with Unit Heat-Up procedure using DCV-73A/3 4.3.3 adjust RCS temperature as indicated by DH2-TI-l & 2 on Panel !8 within the limits of Figure 1 for simultaneous operation of RC pumps and decay heat removal system.
CAUTION:
Prior to starting RC pumps, insure all prerequisite steps per 2102-1.1 Unit Heat-Up are completed.
Ensure the RCS pressure and temperature limits required for RC pump operation rigure 1 are met prior to starting an RCP.
START two R.C. pumps in accordance with RC? operation d.3.4 procedure 2103-1.3.
After the 2nd RC pump is started and in conjunction with the unit heat-up procedure 2102-2.1 the decay heat system will be secured as follows:
CAUTION: Pressurizer spray flow should be in manual concrol thru the normal spray flow path in accordance with procedure 2103-1.3 " Pressurizer U
Operatians".
Ensure a heat-up rate of < 100 F a
3 in any one hour period is being maintained by operation of the turbine bypass valves prior to securing the decay heat system.
[9y 9L 9
14.0
661 2104-1.3 APR 2 3 M Revision 3
//
11/07/77 4.3.5 Frcm Panel !3 STOP decay heat oump DH-P-1A(8).
4.3.6 Frca Panel !4 CLOSE DHV-4A.
I (Decay Heat Loop "A"
& "B" Discharge to RCS.)
4.3.7 From Panel !3 CLOSE DHV-1,2,3 Decay Heat Suction from f
RCS.
4.3.8 From Pane! #3 CLOSE DH-V100 A&B.
l (Decay Heat Suction split isolation).
4.3.9 CLOSE and LOCK DHV-137 (local) D.H. to Pzr. spray line.
4.3.10 CLOSE CHV-lS6 ASB 0.H. Loop ASB to pzr. spray line.
4.3.11 With DHR System isolated from the RCS, energize MUV-16A, B, C
& D (High Press. Injecticn Isolation Valves) CLOSE the folicwing breakers:
1.
On Eng. Safety Features Valves MCC 2-llEA.
(1) Unit 8DR - MUV-16A (Check green closed indication on l
Panel #3).
(2) 'Jnit 90R - MUV-153 (Check green clcsed indication on Panel !3.
2.
On Eng. Safety Features Valves MCC 2-21EA (1) Units 9DR, MUV-16C.
(Check green closed indication on Panel !3.
(2) Unit 10DR - I'UV-16D Check Gen. closed indication on Panel !3.
NOTE:
When the decay heat system is shutdown the DHCCW pumps DC-P-1 A and 18 may be secured in accordance i
with OHCCW system procedure 2104-3.3.
4.4 Special or Infrequent Operations.
1 I93,20
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2104-l.3 g
ff7df17f 3 f:0TE:
.'th the decay heat system in a shutdown node and unit
's heat-up in progress per 2102-1.1 Unit Heat-Up 2102-1.1,
, perform line-up of the decay heat system for E.S. operation as follows:
PlacingtheD&ikSysteminSFASstandby.
4.4.1 4.4.1.1 Verify that the decay heat closed cooling water system is lined up for E.S. operation in accordance with proceare 2104-3.3.
4.4.1.2 Verify thac the nuclear service river water system is lined up for E.S. operation in accordance with procedure 2104.3.1.
4.4.1.3 Verify that pcwer is available to the following decay heat system E.S. valves and the valves are lined ':p as follows:
IfilTIALS POS I T.IO_ft CLOSE0 (1) DH-V4A - Panel #4 Decay Heat Loop "A" discharge to RCS.
CLOSED (2) DH-V4B - Panel #4 Decay Heat Loop "B" Discharge to RCS.
CLOSED (3) DH-VSA - Panel #8 BWST Oischarge to 0.H. Loop "A".
CLOSED (4) DH-V5B - Panel #8 BWST Discharge to D.H. Loop "B".
CLOSED (5) DH-V8A - Panel #8 Sodium Hydroxide Tk. Discharge to D.H. Loop "A".
CLOSED (6) DH-V8B - Panel #8 Sodium Hydroxide Tk. Discharge to D.H. Loop "B".
OPEN (7) DH-V102A - Panel 38 D.H. Loop "A" combined RB f
sump /BWST Suction.
At MCC 2-llEA Lock open tne breakers for DH-V102A, Unit IC3R.
/
gc21 OPEN (8) DH-V1013 - Panel #8 D.H. L'oop "B" combined RB Sump /BWST Suction.
At MCC 2-21EA Lock open the breakers for DH-V102B, Unit 10BR.
i 16.0
h /l 2104-1.3 APR 2 31773 Revision 3 11/07/77 CLOSED (9) DH-V!OCA Panel #8 D.H. Loop "A" Suc tion from RCS.
CLOSED (10) DH-V1003 Panel #8 CH Loop "B" suction from RCS.
4.4.1.4 Verify that power is available to the decay heat pumps DF-P-1A and DH-P-18.
(1) 4160 2-lE-Engineered safeguards switchgear unit ICR breaker racked in and green control pc.'er light lit, l
(D.H. PP DH-D-1A).
(2) 4160 2-2E-Engineered safeguard switchgear unit 1CF brea'ser racked in and green control power light lit, l
(D.H. PP. DH-P-13).
4.4.1.5 Verify that pcwer is available to the following decay heat system non ES valve and the.alves are lined-up as follows:
I'lITIALS POSITION CLOSED (1) DHV-1 Panel #3 decay heat suction from RCS.
CLOSE0 (2) DHV-171 Panel #3 C;iV-1 bypass.
CLOF_D (3) f.J:V-2 Par.el 23 decay heat suction frca RCS.
CLOSED (4) DHV-3 Panel =3 decay heat suction from FCS.
CLOSED (5) DHV-6A Panel #15 decay heat loop "A" suction frori R3 sump.
CLOSED (6) DHV-6B Panel #15 decay heat loop "B" suction froti RB sump.
CLOSED (7) DHV 7A Panel #8 decay heat loop "A" discharge to MU system.
CLOSED (8)
DHV-7B Panel #8 decay heat loop "B" discharge i
to MU system.
THROTTLED (9) DHV-128A Panel #8 decay heat cooler CH-C-1A OPEN discharge.
I93 222 17.0
=
.~
~,
Msu 2104-1.3 Revision 3 fSR 2 3 G73 11/07/77 THROTTLED (10) DHV-128B Panel !8 decay heat cooler DH-C-18 0 PEN discharge.
CLOSED (11) DHV-106A Panel #8 decay heat icop "A" to SFP cooling system.
CLOSED (12) DHV-106B Panel #8 decay heat loop "B" to SFP caoiing system.
CLOSED (13) DHV-lS7 Panel #8 EWST to SFP cooling /3'.lST recire. pump.
CLOSED (14) DHV-lP3A (Local) decay heat 1. cop "A" cross ccnnect.
CLOSED (15) DHV-1938 (local) decay heat Loop "B" cross connect..
CLOSED (16) DHV-ll2A Panel #8 decay heat loop "A" sarple.
CLOSED (17) DHV-ll2B Panel #8 decay heat loop "B' sample.
4.4.1.6 The decay heat remo"al system is lined up for E.S. actuation i
and will start an E.S. signal when RCS pressure decps m
below 1650 PSIG
4.4.2 Long-Term Core Circulation Modes to Prevent Baron Concentration Effects.
s 18.0 b $ ~.
I c.UQRg37373 2104-1.3 -1
- 7 Revision 3 11/07/77
Background:
TopreventconcentrationofboroninthereactorvessElpost LOCA, one of the long-term circulation modes described below should be placed into operation within 24 hours of the LOCA. Action within this time frame is more than adequate to avoid significant baron concentration effects which may occur during natural circulation fica patterns within the reactor vessel, even for the limiting condition of a large reactor vessel inlet pipe break. Injection flow to the RC System should be raintained through two paths while attempting to piace the system.s in one of the long-term circulation nodes whenever possible. The two injection poths can be either the two L.P. injection lines or one LP injection line corbined with one HP injection string (DH pump acting as booster pump for MU pump). The third nethod f:r 1 r ;-tern ul ation (mode 3) is by hot leg injection using the auxiliary.;p line. This method can acco=cda ' > a single failure in that the decay heat drop line is not required. The ficw path for this mode of circulation is from the sump to the operating CH pump through the pressurizer a miary spray line into the pressurizer. This flow path .e able to be implemented as required for backup of the n. first two modes. In the event MCC 2-42B is lost and RC-149 cannot be operated, connect temporary power to RC-V1, 3, and 9 149 using Standing Paintenance Procedure later The fourth method of long-term circulation (mode 4) is established by providing reverse flow through the Decay Heat drop line 19.0 I93 224
bd 'XFR t '3 gy *; 2104-1.3 Revision 3 pp 11/07/77 into the "B" RC Loop hot leg. This fleu path provides flow from the operating DH pump through the DH pump discharge cross-connect line and back through the idle DH pump recirc and suction line, and back up the DH drop line in reverse ficw to result in hot leg injection to the core. This method should be used if the methods discussed above are not functional, (i.e. use Mode 4 if Modes 1 and 2 are not operable). ~ 4.4.2.1 Mode 1 Forced Circulatien Using Decay Heat Drop Line. l NOTE: This procedure will 'stablWh DH drop line flow through the "A" CH pump. This mode should only be attempted if both LP injection strings A and B are operable. This mode further assumes that the "B" CH pump ic 'a Hng suction from either the Reactor Building Sump or the BWST and is discharging either through the DH-V43 valve or both through the DH-Vd8 and into the appropriate T.ake-up pump suction valve. 4.4.2.1.1 OPEN motor-operated DH drop line valves DH-V1 or 171 and DH-V2. 4.4.1.1.2 ENSURE that cross-connect valves DH-Vl93A, DH-Vl93B, DH-V100A, DH-V1003 between LP injection strings A and B are closed. SECURE DH-P-1A and BS-P-1A (Reactor Building Spray Pump connected to the same suction line). 4.4.2.1.3 CLOSE DH-V102A and OPEN valve DH-V100A in DH drop 2 line. 4.4.2.1.4 CLOSE DH-V123A and DH-V6A. CPEN CH-V3. l 93 225 20.0 .mm-m.-
Yet 2104-1.3 APR 2 3 m - Revision.3 11/07/77
- 3 l
START DH-P-1 A and slowly increase flow by throttling 4.4.2.1.5 open DH-V128A. Minimize the duration of time thit DH-P-1A is on recirculation to reduce pump overheating. Ob' serve p"mp 'lcw indicator DH-1-F12 and pump discharge ure 'or sy ptoms of cavitation and entrainment pr( of vapcr or g2s (i.e. 'cratic flew and abnormal pump ne -T. 'When time per mits, throttle CH-V122A as i ncw ing suction frr nece uar;. ii-T-1A 9e ! cop """ ht,t leg only. 4.4.2.1.6 [f the Mt! p> r is taking suction from DH-P-18, the f makeup oump ma/ now be secured if flow has been satisfactorily established in Step 4.4.2.1.5 abcve. !OIE: if u..Jeury riva cannot be estabiished, maint_in the two injection paths with LP injection from DH-P-lS and HP injection fic. :,cugh "U-V16C and t'U-V16D and then es a: 'sn one of the long-term circulation flow paths described in the following sections. Af ter completion of Step 4.4.2.1.6 above, if it is 4.4.2.1.7 desired to determine if the breal location is high enough in elevation to operate only one low pressure injection string (i.e. is the hot leg flooded?) proceed as fel':.;s: ~ t;0TE : Do no. attempt unless DH flow in A lcop is 1500-2000 gpm or more (i.e., indicative that creak has occurred in an elevated ~ 226 21.0
2104-1.3 t Revision 3 AP 11/07/77 $2 portion of hot or cold leg piping, on OTSG side of cold leg piping, or in DH or CF piping). This flow rate is necessary to ensure that sufficient heat removal capability is available to prevent boil-off assuming "A" DH line is intact. While continuously observing Icw pressure injection string A indicated flow rate (DH-1-FI2) for erratic behavior, sicwly decrease ficw rate in low pressure injection tring B by throttling DH-V1238 and then secure DH-P-18. Coolant from the sump is not beir] pu.nueJ to the reactor sessel at this point (i.e., not providing overficw out the break). If suction to the "A" low pressure injection pump is maintained, it is indicative that (1) the RC System is filled to above the hot leg elevation (2) the break in the RC System is above this elevation and (3) the "A" low pressure injection string is intact. The "B" low pressure injection string may then be placed back in operation (taking suction from the Reactor Building Sump) or operated periodically to makeup for volume contraction -j as "A" low pressure injection string redLces the reactor coolant ten'perature. l93 227 22.0
1.\\ OJ7 J2 6 y 2104-1.3 f yy APR 2 3 $73 4.4.2.2 Mode 2 Gravity Draining Reactor Coolant Hot Leg to the Reactor Building Sump Via the D.H. Drop Line. ,-{ 4.4.2.2.1 Install portable flow indication ac DH-V237 and DH-V238. ~ 4.4.2.2.2 DH-P-1A (if I H-P ^1B is idle, use component numbers in parenthesis) is idle from an unsuccessful forced circulation mode (Mode 1) attempt. 4.4.2.2.3 VERIFY that valves DH-/1 or 171, DH-V2, DH-VlCDA (1003) are open. 4.4.2.2.4 VERIFY that valves DH-V3, DH-V6A (63) and DH-v102A (1023) are f closed. 4.4.2.2.5 CLOSE idle DH Pump Cooler Outlet Valve, DH-V128A (12SB) and l close Cross-connect Valve, DH-Vl93A (1938). a.4.2.4.6 OPEN RB Sump Outlet Vulve CH-V6A (6B), cnd CH-V102A (1023). f 4.4.2.2.7 CPEN Di-V3 and OBSERVE the OH dmp line flow at local fiou indicator installed in st.p 4.4.2.2.? 4.4.2.2.S If no flow is indicated go ta step 4.4.2.2.9. If fis.1 is I indicated, proceed to step ".4.2.2.10. l 4.4.2.2.9 This step will provide cool water ficw back up the D.H. drop line. With the gravity drain ficw path established, open D.H. discharge cross-connect valves OH-Vl93A and DH-Vl938 and then open pump suction valve DH-V100A (DH-V1003). Close RB sump outlet valve DH-VSA (DH-V63) and DH-V102A (102B) Monitor the operating low pressure injection ficw rate to ensure no significant decrease occurs as this lineup established a flow path from the operating low pressure injection string through the cross- -j connects and the idle DH cump recirc line and backwards up through the DH drop line. When the flow is established in the 23.0 193 228
gd / (j). C AFR 2 3 LVJ l 2104-1.3 Revision 3 11/07/77 DH drop line, close DH-V100A and DH-V102A (DH-V1008 and DH-w V1028) and re-establish the gravity drain flow path as described ~ above in steps 4.4.2.2.1 through 4.4.2.2.7. 4.4.2.2.10 ffaintain infection flow frcm the Reactor Building Sump to the reacto. vessel through two injection flow paths by supplying flow with the operating DH pemp through the LP injection lines and/or to the HP injectior, pump suction as required by 2202-1.3. 4.4.2.3 3 Hot Leg Injection Using Pressurizer Auxiliary Spray Line. NOTE: This procedure is to be used for long-term core circulation only if one of the icw pressure injection strings is
- c. operable or if satisfactory flow cannot be established by the procedure of moda #1 or of mode #2.
4.4.2.3.1 CLOSE prassurizer spray line motar-cpc.cated valves RC-V1 and l RC-V3. 4.4.2.3.2 CLOSE the idle Decay Haat Pu.p Suction Valve CH-7102A (DH-V102B) to prevent possible backflow through the pump recirculation line. 4.4.2.3.3 OPEtt the auxiliary spray line isolation valve DH-V186A (DH-j VIS68) for the operating DH pump, and DH-V187. 4.4.2.3.4 OPEri RC-V149 to establish the spray flow path. 4.4.9.4 Mode 4 Reverse Flow Through The Decay Heat Drop Line Into "B" Reactor Coolant Loop Hot leg. j i 4.4.2.4.1 ESTABLISH operation with DH-P-1A (or if DH-P-1B is used, refer,1 2 to component numbers in parenthesis) with discharge cross-connect valves DH-Vl93A and DH-Vl938 open and ficw split l9} ]g 24.0 ~.
j,b cN Y 2104-1.3 C 2 3 W3 Revision 3 11/07/77 between the two low pressure injection lines by throt$ ling control valves DH-V128A and DH-V1288. 4.4.2.4.2 OPEN Decay Heat drop line motor-operated valves DH-V1 or 171 and DH-V2. 4.4.2.4.3 If DH-P-1B (DH-P-1 A) is the idle pump, secure BS-P-1B (BS-P-lA) as the pump on the idle suction line. CLOSE the associated motor-operated suction valve, BS-V3B (BS-V3A). CLOSE motor-operated reactor building sump outlet valve associated with the idle decay heat pump, DH-V6B (DH-V6A) and DH-V102B (102A). 4.4.2.4.4 If DH-P-1B (DH-P-1A) is the idle pump, open DH-V10CB (DH-f V100A). Note operating DH pump discharge pressure as indicated on DH-5-PlA (DH-5-PIB). 4.4.2.4.' Cpen motor-eperated d a y ncat drop line valve, CH-V3. This establishes reverse flew frem the operating DH purp discharge back through the idle pump recirculation line and the decay heat drop line to the "B" reactor coolant loop hot leg. This reverse flow should be c:nfirmed by a slight decrease in indicated low pressure in'jection ficw rate (DH-1-FIl and DH, FI2) and/or by a slight decrease in DH pump discharge pressure (DH-PI-464 or 466). N 25.0 ~ lO'd 230
~ Y. h: iMI UNIT #2 2104-1.3 2104-1.3 Revision 6 02/27/78 APPENDIX A Valve Line-Up System: Valve No. Description Posi. ion Initial REACTOR BUILDING FLOOR ELEVATION 280'6" OUTSinE atCONDARY SHIELD DH-V1 Primary Loop to DHR System Closed DH-V171 DH-V1 Bypass Closeo REACTOR BUILDING FLOOR ELEVATION 280'6" OUTSIDE SECDNDARY SHIELD CH-Vi72 DH Suction Line to RB Sump Drain Closed DH-V173 DH Suction Line to RB Sump Crain Closed DH-Vl95 Test Conn. Downstream DH-Vl72 Closed DH-V2 Primary Loop to DHR System Closed DH-V161 DH Suction Line to LMDS Drain Closed Wired & Sealed DH-V162 CH Suction Line to LWDS Drair. Closed Wired & Sealed CH-Vl97 Test Conn. Downstream DH-V161 Closed Wired & Sealed DH-V159A DH Loop "A" to Primary Drain to Closed LWDS Wired & Sealed DH-V160A CH Loop "A" to Primary-Crain to Closed LWDS Nired & Sealed DH-V211A Test Conn. Downstream DH-VlS9A Closed Wired & Sealed DH-V159B DH Loop "B" to Primary-Crain to Closed LWDS Wired & Sealed DH-V1608 DH Loop "B" to Primary-Drain to Closed LWDS Wired &-Sealed DH-V211 B Test Conn. Downstream DH-V159B Closed Wired & Sealed DH-V215 DH to PZR Aux. Spray Line Sump Closed Drain Wired & Sealed DH-Vl92 DH to PZR Aux. Spray Line Sump Clused a Drain Wired ? Sealed DH-V203 Test Conn. Downstream DH-V215 Closed Wired & Sealed f b ]7 26.0
/,)) "/ ~ Uf 13 2 8 sn. 2104-1.3 Revision 6 TMI UNIT #2 02/27/78 2104-1.3 ~, APPENDIX A Valve Line-Up System: Valve No. Descriotion Position Initial FUEL HANDLIf,G BUILDING FLOCR ELEVATION 280'6" DH-V225 Inst. Root Valve Open DH-V3 Primary Loop to DHR System Closed DH-V4B DH Loop "S" to Pricacy Closed DH-213B Test Conn. Upstream DH-V43 Closed Wired & Sealed DH-214B Test Conn. Upstream DH-V4B Closed Wired & Sealed DH-V4A DH Loop "A" to Primary Closed DM-V213 ^ Test Conn. Upstream DH-V4A Closed Wired & Sealed JH-V214A Test Conn. Upstream DH-VCA Closed Wired & Sealed DH-VlS6A DH Locp "A" To PZR Aux. Soray Line Closed CH-V1363 DH Loop "S" to PZR Aux. Spray Line Closed MAKE-UP VALVE ALLEY ELEVATION 280' 6" DH-Vl99 Test Conn. Downstream DM-V3 Closed Wired & Sealed DH-V200 Test Conn. Downstream DH-V3 Closed Wired & Sealed DH-V188 From SFC to DH Suction Locked / Closed DH-V7A DH Loop "A" to MU Pump Closed DH-V147B BWST to MU Pump Locked /Open DH-V7B DH Loop "B" to MU Pump Closed b DH-V147A BWST to MU Pump Locked /Open AUXILIARY BUILDING 280'6" ELEVATION DH-157 BWST to SF CLNG System Closed DH-120 SF CLNG System to BWST Closed 32 27.0 ?
[ AFa 2 3 gag f5 2104-1.3 Revi.sion 6 TMI UNIT #2 02/27/78 2104-1.3 APPENDIX A o" Valve Line-Up System: Valve No. Description Position Initial DH HEAT VAULT A FLOOR ELEVATION 258'6" DH-VSA BWST Discharge Closed DH-V129A DH-DPT-1 Inst. Rcot Open DH-V130A DH-DPT-1 Inst. Root Open DH-V201B Test Conn. Downstream DH-V6B Closed Wired & Sealed DH-V2028 Test Conn. Downstream DH-V6B Closed Wired & Sealed CH-V201A Test Conn. Downsteam DH-V6A Closed Wired & Sealed DH V202A Test Conn. Downstream DH-V6A Closed Wired & Sealed DH-V179A DH Cooler - TA Vent Closed 6 DH-V180A DH Cooler - 1A Vent Closed DH-V128A DH Cooler l A Discharge ("otor) Open DH-Vl93A DH Loop "A" Cooler Cross Tie Locked Closed DH-V108A DH Discharge Cross Connect Locked Closed DH-VlC8B DH Discharge Cross Connect Locked Closed CH-V109 DH Discharge Cross Conn. to Closed SFC/DH Suction DH-Vil6 BWST Re .c. Line Closed DH-V106A DH Loop "A" Discharge to SF Closed DH-V178A DH Cooler lA Discharge.tanual)
- Ope, 1
DM-V110 DH Discharge to DH Suction Closed DH-Vil2A Sample DH Loop "A" Discharge Closed DH-V101A SWST Recirc. to DH Loop "A" Closed Sv tion j o } 0 } '7 q DH-V126A DH Cooler lA Press Test Cor.n. Closed 28.0
~' ~ R :. 3 143 3 d Q~~ 2104-1.3 Revision 6 TMI UNIT #2 02/27/78 2104-1.3 n-APPENDIX A Valve Line-Up System: Valve No. Description Position Initial CH-V127A DH Cooler 1 A Press Test Conn. Closed DH-V181A DH Cooler lA Drain Closed DH-V182A DH Cooler lA Drain Closed DH HEAT VAULT A FLCOR ELEVATION 258'6" DH-V221 PX Isolation Closed DH-V-222 PX Isolation Closed DH-V170A DH Pump 1 A Combined Drain Closed DH-VlS4A DH Pump 1A Drain Closed DH-V169A DH Pump 1A Drain Closed DH-V167A DH Pump 1A Vent Closed DH-V16SA DH Pump 1A Vent Closed DH-V122A Press. Test Conn. DHP 1A Suction Closed DH-V183A DH Pcmp 1A Drain Closed DH-V131A DH-DPI 1447 Inst. Root Open DH-V124A DH-DPI 1447/DH-P3 463 Inst. Root Open DH-V123A DH Pump 1A Discharge Press Test. Closed Conn. DH-Villa DH-SPI ost. Root Open DH-V125A DH-PT 464 Inst. Root Open DH-V100A Primary to D.H. Loop "A" Suction Closed DH-V102A BNST/RS Sump to DH Loop "A" Open Suction DH-121A DH-P1 2003 Inst. Root Open ,DH-V5B BWST Discharge Closed 29.0 ?
f,f2R03lill - ~ hp/7 14.1.3 Re'yision 6 02/27/78 TMI UtlIT #2 2104-1.3 APPEt1 DIX A Valve Line-Up System: Val ve I.'o. Description Position Indial later "A" Pump Cyclone Separator Inlet Closed Later "A" Pump Cyclone Separator Outlet Closed s later "A" Pump Cyclone Separator Crain TH ) la ter "A" Pump Cyclone Separator Inlet Open Later "A" Pump Separator Outlet Open 2t ns Later "A" Pump Cyclone Separator Drain TH 3g D.H. VAULT B FLOOR ELEVATION 258'6" DH-V129B DHl-DPT-2 Inst. Root Open DH-V13CB DHl-DPT-2 Inst. Root Open CH-V1288 DH Cooler 18 Discharge (Motor) Open DH-V1218 DH-P1 2004 Inst. Root Open DH-Vl938 DH Loop "B" Cooler Cross Tie Locked Closed _ DH-Vll2B Sample CH Loop "B" D Hcharge Closed DH-VIOSB CH Loop "B" Discharge to SF Demin. Closed DH-V102B SWST/R6 Sump to D.H. Loop "B" Suction Open DH-V178B DH Cooler IB Discharge (Manual) Open DH-V126B DH Cooler 18 Press Test Conn. Closed DH-V127B DH Cooler 1B Press Test Conn. Closed DH-V1818 DH Cooler IB Drain Closed DH-Vl82B DH Cooler 1B Drain Closed DH-V1008 Primary to D.H. Loop "B" Suction Closed 30.0 I73 235 ~
f APR23EU9 2104-1.3 [hf:h-Revisi6n 3 11/07/77 THI U:llT #2 2104-1.3 APPENDIX A Valve Line-Up _Sys tem: Valve No. Description Position Initial DH-V101B BWST Recirc. to D.H. Loop "B" Suction Closed DH-V1708 DH Pump 1B Ccmbined Drain Closed DH-V169B DH Pump to Drain Closed DH-Vl84B DH Pump 1B Crain Closed DH-V1678 DH Pump 1B Vent Closed DH-V163B DH Pump 1B Vent Closed DH-V223' DH-P-18 Minimum Recirc Px Test Closed DH-V224 DH-P-1B Minimum Recirc Px Test Closed D.H. VALVE FLOOR ELEVATIO 1258' DH-V122B Press. Test Conn. DHP 1B Suetion Closed DH-Vl338 DH Pump 18 Drain Closed l_ CH-V1318 DH-DPl 1446 Inst. Root Open DH-V124B DH-DPI 1446/DH PS 465 Inst. Root Open DH-V1238 DH Pump 1B Discharge Precs Test Conn. Closed DH-VillB DH-5-PlZ Inst. Root Open DH-V125B DH-PT-466 Inst. Root. Open DH-Vl79B DH Cooler IB Vent Closed DH-V180B DH Cooler 1B Vent Closed t 31.0 i 93 2.36 i e.
-
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Q krh 4 a 9 a 2104-1.3 4U- / Revision 3 11/07/77 '~ TMI UNIT #2 2104-1.3 ff' APPENDIX A Valve Line-Up System: Wlve No. Descriotion Position Initial Later "B" Pump Cyclone Separator Inlet Open Later "B" Pump Cucione Separator Outlet Cpen 2 Later "B" Pump Cyclone Separator Drain TH C d Later "B" Pump Cyclone Separator Inlet Open Later "B" Pump Cyclone Separator Outlet Open Later "B" Pum, Cyclone Separator Drain 2 Turns TH Closed RB SPRAY VAULT "B" FLCOR ELEVATION 258'6" DH-V6A CH/RBS Suction from RB Sump Closed CH-V6B DH/RBS Suction frcm RB Sump Closed DH-V233 Test Conn. Downstream DH-V-6A Closed DH-V234 Test Conn. Cc nstream DH-V-6A Closed DH-V235 Test Conn. Dcwnstream DH-V-6B Closed CH-V236 Test Conn. Downstream DH-V-6B Closed BORATED WATER STORAGE TANK & SODIUM HYDROXIDE TANK JH-Vl34A Sodium Hydr. To BWST Discharge Locked Open DH-V134B S,dium Uydr. to BWST Discharge Locked Open DH-V8B Sot'ium Hydroxide Tk. Discharge (Motor) Closed DH-V8A Sodi2m Hydroxide Tk. Discharge (Motor) Closed DH-V137A Demin. Wtr. to Sodium Hydr. Supply Closed Line "B" CH-V137B Demin. Wtr. to Sodium Hydr. Supply Closed Line "A" DH-V136A Sodium Hydroxide Supply Line "A" Drain Closed 193 237 32.0 I
7, 2104-1.3 Revision A)R 2 3 Egg ' 11/07/77 a2 TMI UNIT #2 2104-1.3 /$' APPENDIX _A Valve Line-Up System: Valve No. Description Position Initial DH-V176 Sodium Hydroxide Supply Combined Drain Closed Locked DH-V1338 Sodium Hydroxide Tk. Discharge (Manual) Open DH-V135B Sodium Hydroxide Supply Line "B" Drain C'osed Locked DH-V133A Sodium Hydroxide Tk. Discharge (Manual) Open DH-V216 BWST Sample Conn. Closed DH-V217 BWST Sample Conn. Closed Locked Dh-Vlfd Sodiun; Hydro. Tk. Outlet Open PH-Vla0 NP Supply Closea ac-V139 CH-9-P1 Irst. Poot Open CH-V: 5' Sodicai Hydro. Tk. Jrain Closed DH,144 Tedbcs Hydro. Tk. Drain Closed DM-vl43 Sca;um Hydro. Tk. Recirc. Closed CH-V142 from Caustic Mix Tk.. Closad DH-V141 Sodium Hydra. Supply to Tk. Closed DH-V145 SoJaum Hydro. Tk. Sample Closed DH-V175 Sodium Hydro. Tk. Sample Closed DH-V165 DH-7-LT Inst. Root Open DH-V!64 DH-7-LT Inst. Root Open DH-V138 Sodium Hydro. Tk. Vent Closed i }93 2}8 33.0 ?
N# 2104-1.3 APR 2 31979 : Revision 7 9h 03/17/78 TMI UtlIT #2 2104-1.3 APPENDIX A Valve Line-Up System: Valve i;o. Description Fosition Initial CH-Vil4 BWST Over-Flow Closed DH-V149 BWST Cutlet Locked Open DH-V229 Upstream Valve for DH-U2 Open DH-V230 Do'.,nstream Valve for DH-02 Open DH-V189 Demin. Utr. to BWST Closed DH-V232 Inst. Root Open DH-Vl94 DH-3-LTl Inst. Root Open D'f-V118 SWST Drain to Aux. Bldg. Sump Closed DH-V152 BWST Drain to Aux. Sldg. Sump Closed DH-Vl63 BS Pump to BWST Closed DH-V132 DH-3-LT2 Inst. Root Open DH-V231 Inst. Root Open DH-V2198 DH-P-2B Suction Open DH-V219A DH-P-2A Suction Open DH-V226A CH-P-2A Disch. Inst Root Cpen DH-V226B DH-P-2B Disch. Inst. Root Open DH-V-218A DH-P-2A Discharge Open DH-V-2188 DH-P-2B Discharge Open t 34.0 193 239 ~
i APR 2 3 $73 ~ 2104-1.3 Revision 6 c/. 02/27/78 TMI UNIT.32 2104-1.3 APPENDIX A Valve Line-Up _Szstem: Valve No. Descriotion Posi tion Ini ti al FUEL HANDLING BLOG. FLOOR ELEVATION 323' DH-V187 DH to Aux. PZR Spray Line Locked Closed DH-V205 Tes t Conn. Downs trer.1 DH-V187 Closed Wired & Sealeu CH-V206 Test Conn. Co',instream DH-V187 Closed Wired & Sealed DH-V237 Inst. Root at CH-V187 Cpen DH-V207 Test Conn. upstream r '-V187 Closed Wired & Sealed CH-V208 Test Conn. upstream GH-V187 Closed Wired & Sealed N o 35.0 l I
LM IJR E 3 753 2104-1.3 ed/ Revision 3 -49 11/07/77 APPENDIX B Signatures of those performing / supervising valve line-ur.. Valve Line-up Signature Sheet Opera tor Opera tor Shift Foreman or Initials Signature Shift Date Sucervisor Sig. Remarks N 6 9 36.0 f 2d[
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