ML20126D134
| ML20126D134 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah  |
| Issue date: | 03/31/1980 |
| From: | Benton C, Record D, Jacqwan Walker TENNESSEE VALLEY AUTHORITY |
| To: | |
| Shared Package | |
| ML20126D128 | List: |
| References | |
| EOI-1, NUDOCS 8004170229 | |
| Download: ML20126D134 (29) | |
Text
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DISTRIBUTION IC Plant Master File to , .
ESTRCE':C OPERATING INSTR"CTION Superintendent
"" L 11' Assistant Superintendent (Cper.)
1p Assistant Superintender*. (Maint.)
ECI-l Administrative Supervnor Maintenance Supervisor (;1')
LCCS CF REACTOR CCOLANT Assistant Maintenance Supervisor (M)
Ma intenance Supe r'n sor (E)
Assistant Maintenance Supervisor (E)
Units 1S2 Maintenance Super'.isor (i)
Results Supervisor ic Operations Supervisor Quality Assurance Supervisor e
_ ___ - -_. .- -- - - - __ j r g ; tv Public Safety Services Supv Chief Storekeeper Preop Test Program Coordinator Outage Director Chemical Engineer (Results)
Radiochem Laboratory Instrument Shop Reactor Engineer (Results)
Instrument Engineer (>Sint. (I))
Mechanical Engineer (Results)
Staff Industrial Engineer (Pl. Sys.)
1r Training Center Coordinator PSO - Chichamauga Engri; Unit - SNP Prepared by C. T. Benten Public Safety Services - SNP sc Shift Engineer's Office Revised By: J. R. Walker sc Unit Control Room l Submitted By: p%OL
)
q QA&A Rep. - SNP !
.- 9to- Health Physics Laboratory l Supc 7isor ' ' '
Asst Dir NUC PR (Oper), 727 EB-C l PCRC e.'iew: 7 // ;, I /00
-u _ _l',l _ Nuclear Docu=ent Centrol Unit , 606 E3-C Superintendent, VP'!?
g 1 cap ; Superintendent, BFNP
} -
, Superintendent, BENP m NEB, W9C174C-K Approved By:[\6uperfitencen
[tgdjg hD it Q3 h._ Supv., NFHPS ROB, MS 4
in NRC-II:11 ,
Power Security Officer, 620 CSI2-C l Nuclea r Materials Coordinate r-1410 CUBE-Date Approved: \' 5k\ b Manager. OP-QA&A Staff
\ !" Resident NRC Inspector - SNP sr NSRS, 249A F.EE-K ir Technical Support Center Rev. No. Date Revised Pages Rev. No. Date Revised Paees R 2/9/80 All o .2/14/80 4 In y i/, N -
All The last page of this instruction is Number )E 4()04170 % 4
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'"he cbjectives of these instructions are to s.oecif.r rec.uired e er2:Or ::icn and .
precautions necessary to:
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.s .... . o the ruel cladding and release of excessive radicnetivity.
- 2. Maintain leng; term shutdown and cooling of the reactor by recirculation of spilled reactor coolant, injected water, water from melted ice bea and centain-ment cpray cysten drainace.
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ns of ECI-0, i= ediate 4A. O L;:% ;.c-mnte-t r.um - r .m p
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to step and then "M" complete stepthat the cecresces sppears imminent E/2T re.tc..a.l.v Icv such level a CAUTION:
The D/G's periods of time. should not be operated at idls E through L pared for restart. If the diesels are shut downe or minimum lead for extended I.!O1F;: , they shculd be pre-Verify and that the Post Accident Monit recording.
Centainment Pressure PdI-30-ht , h5 2.
Refueling ' dater Sterage Tank Level 50, 51 LI 6 3.
L.
Steam Generator '4ater Level (narr Steam Cenerator Water Level (tide :c.< rance) LI-3-39, 52, .
- 5. Stes: rence) LE-L3, 96 Line Fressure PI-1-2A, 23, 9A !
- 6. , 93, 20A, 203, 27A, 273 ,
7.
Pressuriter Water Level LI-68-320 , 335A Reactor coolant system temperature T3 63
- 3. -
-1, 60 i Reacter coolant 1 NOTE: sy tem pressure PI-6S-68A, FF-63-66 l i
The precess variables referred to i i 1 '
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- enitored by mere than one ainstrument tin thic instruction are ty channels of this instruction. should be checked for consist on channel.
The redundant F
.~ a : ency while performin; the steps i n.ne pre:suriner i tion with other reactor coola n twater level indication should alway 4
condition and to initiate manual eroperatsystem actions, indications to evaluat s
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i under the action of the safeguards pu. .ps, check that the recirculation su .7 vater level instru.entatien indicates an increase in water level in the
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- 01. tne sy pto.s a.n r.vi-0 nust be ccnducte a .
C AUT'O'1 : Reference Leg Heatuu: High energy line breaks inside containment !
can result in heatup of level measurement ref. leg's on the S"r's 3,.,. d ~r _m. . . *k.
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therefore it vill be necessary to control the levels ac fc110vs during post accident l
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and/cr maintain between LO% and 71~4' narrev range water level (?AMS). If narrow range water level increases in an uner.plained manner in ene steam 3 ....a*.~.,
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Il0TE: Manitor the primary water supply (Cendensate Storage Tank) for the a ny. 4 _'m 4 s" . .- 'e- a d"n.+ a. ". r.u~., a a. d "" ~..'. .- a. .a a. k..d. . . .- a _' m
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,y. . .o auto evitch vver does not occur by the tine the condensate stcrate tank level decreases to 6", manually svitch over.
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. .a Safety Injection can be terminated IJ:
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THEN (5) Reset safety injection and stop safety injecticn pumps not needed for
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s the diesel powered energency busses.
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c E0I-1B subsequent operator actions in conjunction with this procedure to reestablish operation of safety equipment that a
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EDI-1A - Units 1 and 2 l i
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(o) Flace all safety injection pamps not needed to provide normal charg'ag flow in standby mcde and maintain operable safety injecticn flovpaths.
(?) Icciate safety injecticn flew to FCS Celd legs via Scron Injection Tank and establich ner=al charging ficv. l l
CAUTICN: Mcnitor the primary cyctc= (ECS) throughout thic inctruction
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coeling exists when; i i
l l
(a) 5 or more core o exit thernccouples exhibit readings at '
above 1200 F, (en ec=puter)
_OR (b) If the high range readings frca the core exit ther=c-couples (en ec puter) are not available, a condition of inadequate core cooling exists when:
The hot lec ETT'c are pegged high er five cr_mcre incere therncccuples are off-scale above 700*F and SI !
f1cv is not being delivered to the E03 and AFW is not bein; deliverei to the intact cteam ceneratere.
It conditions in (a) er (b) are determined to exist '
see Appendix D of this procedure for instructions to restore core cooling.
ULTE: Use ec puter subcooling program and Appendix A to determine cargin of subcooling being maintained.
CAUTICN: If reactor coolant pressure drops belev the low pressuricer pressure setpoint for safety injection (1870 psig) or ,
pressuricer water level drops belev 205 of span folleving I terr.ination of cafety injec-icn flev e- reactor ccclant sub-cooling drops belev 40*F.
MAlUALLY REIMITIATE safety injection to establish reactor coolant pressure and precsuricer water level. Oa to Secticn
)
III of E0I-0 to reevaluate the event, unler; this reevaluation 1 hac already been performed.
1 CAUTIGH: Steppin: " Ti r' 'nu- --
r:
1 pumps ana _: .. m a ey ..,a ac.1 pc p ean m ac p ..;., .
motor overheating or~ reduced motor life. Hence, if pumps o
i are restarted once after termination, an additional 15 F of sub-cooling should be added to the required sub-ccoling prior to the second termination of the high head pumps.
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(c) Reestablich normal makeup and letdown (if 1ctd:vn .. J _ n 20 ) ts maintain preccuriner water level and to caintain reactcr cociant pressure ut valuec reached when safety injectica is terr.inated.
Encurc that water allition durtng thi; process does not result in dilution of the reacter coolan* cysten bcron concentratien.
(9) Reestablish operation of the pressurizer heaters. When reactor coolant pressure can be controlled @y pressurizer heaters alone, r,eturn makeup and letdown to preocuriner water level centr:1 caly,
- heaters).
(see appendix r, for ava11 ability of. rea (10) Monitor either the average temperatu're indication of core exit thermo-c -"rles (if svailable) or all vide range reactor coolan; temperature TH \ ^ ' **# I '*
- E* " * **
- saturation temperature at RCS indicated precoure.
o 1 If 50 F indicated subcooling is not nresent, then attempt to establish n . .
50*F indicated cub:coling by cteam dump frem the steam generators to ,
I the condenter er the atrecrhere, (see Appendix 0 for guideline 0 )
relative to natural circulation if hCF's are off). l CAUTION: If steam dump ic necessary, reduce the steam cencratcr prescure to c,c,- f p si s s c_v_ u, psig ce2cw the lowest ster safety valve setpoint) and maintgin a reactor coolant cocidern rate of no more than 50*F/HR, consistent with plant make-up capability.
If 50 F indicated subcooling cannot be established or maintained, then manually reinitiate safety injection. Go to Section III of EOI-0 to re-evaluate the event, unless this re-evaluatien has already been performed.
(11) Perfer= a controlled cooldown to cold shutdevn conditiens using Normal C001down procedure if req; ired to affect reeairs. Maintain subcooled :nditi ns (at lenct 50"? indicated subcoolir.g) in the reactor coolant system. If sub::oled conditions cannot be maintained, 50 to Step D.
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maintain necessary safety injection pumps operating. If any safeguards equipment is not operating, attempt to cperate the equipment from the ;
control room or locally. Effect repairs if necessary. If reactor coolant !
prescure is above the 1cv head safety injection pump shut-off head, l manually reset safety injection so that safegt rds equipment can be controlled by manual action. Stop the lov head safety injection pumps and place in the standby mode.
CAUTION: Whenever the reactor coolant pressure decreases below the lov head safety injection shutoff head, the lov head safety injection pumps must be manually restarted to deliver fluid to the reactor coolant system.
~ h'
SQNP E0I-1A - Unit a 1 and 2 Page b of 15 : .
Rev. 10 y,.
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r E. Trancfer UR-L5 to one cource range and one intermediate range channel.
F. *. 2rify centrol roar ventilation inclation ( cee 20I-30.13)
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equipment trancfor hatch ccver in place (734' elelevation to lower elevation).
H. Rec.':e c t t.erformance of SI-268 to verify. r.ecitien of F b contacts (failure Of T h contacts may prevent recetting CI signal).
I. Declare Gas Ccndition I J. leave both trainc of ECT3 in cervice till recovery pertien of procedure is carried cut.
Verify A-A and 3-3 contain=ent air return f anc in cervice (10 min time delay after phase 3) and suction dampers 25-30-72 and 1S-30-73 epen
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- '. Etcp A1L reacter cociant pumps after the high head cafety injection pump operation has been verified 9nC when the vide ran;e reacter ecclant prc: cure decreasec to 1550 paig.
CAUTICM- If component cooling water to the reactor coolant pumps is icolated on a containment phase "B" signal, all reactor coolant pumps are to te stopped within 5 minutes because of 1cca of =cter bearing ecoling.
C A'JTICN : If reacter coolant pu=pc are stoppel, the seal injecticn flew should be maintained.
NOTE: The conditions given above for stepping reacter ecolant pumps
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N. Verify UHI accumulator icolatien valvec close en lov level after accumulator liquid is dumped.
O. Verify cola leg accumulators dump their centent: if BCS pressure decreaces
.ce,cw ;,~,v,0 psig.
' "-a - 'na ec*ericed by reactor coolant prescure quickly a s .c . :2. .. ; . _ . . - x 2. sm.eca;or pressure, go to ctep T. In the case of a break charactericed by a slowly decreasing reactor coolant pressure or stabilized reactor coolant system prescure above the lowest steam system safety valve setpoint, (106h poig), the following additional manual actions should be taken to aid the cooldown and depressurization of the reactor coolant system:
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valves and transfer the steam dump eentrol to steam header pressure
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temperature (FAXS) and censequently the reneter coolant prescure.
- 2. If the nain condenser is not in service, dump steam to the atmosphere with the steam relief valves to lower the reactor coolant temperature
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- a. s s " *. a. .
CAUTIC:! : Reduce the stcan generator pressure to co~ psig (.200 pais - . .
below the lowest steam system safety valve setpcint) and m..,t..+ ... ,4n a .-n.nn+.,. . . ,. c o., an+. n. m n.., a.n.n. .v.+, . . . . o e. .. o _- n. .-a. th,n _
50'F/HR, consistent with plant make-up capabilitv.
n.
s .T. ., . m,ge. , .oy .e . e. a, -.. (ss -age
- a ) 4 e. .. a -. m. . 4....4..a.,..+, ., w . n . m. .e. .i d a .- a .
- o . . ".' "-_' d
.a -
% % . ,. .e. t o y- ,. .,.cw... ... 4. e. ,, . ,,
p . e. . 4 m.. a m, ,..,. es. ~..
. ., w..o. p,.,..e......, .m...
follows:
- 1. Periodically check auxiliary building area radiction =cnitors for d +. '. e c. . 4 . ....^"_' a e.'. .- _, a. . -
- 7. .' a.';....'^.-...
e - . *r+ 1eab.a e 4..- da.'e
. e . .a.#. a..e.,*.'.-
isolate the leakage and implement the reauired radiation protection.
- m. , .. a..,.e
., .w . . ~ n,...,_.._..,,_.4._.44 m . u. . - .
. . . . .. - .,, 2_,.
9
-. k'h i. ' ' e .k.a. y. " ' a n +., i oa d.n cold 1e . - 4 e- 4.og e
- i-~.. .~^ . . . A e , . a k.e. "*.. ^.,vi e ..d .r.e
. , . .' o.- .a.o-evaluation of equipment in the plant. See Appendix G for checkoff list. Follev radiation control methods while performing checklist.
- 3. Prior to the time specified for the plant switchover to the cold leg recirculation mode: 1
- a. Re-energize breakers, as required, for valves needed to affect switchover.
. .o ..
, . . . .2.m.. . . . ,,.. , .... . .w. .,. . 1. m. ... . . _ . .. , . a.
.. 4_ .o .%...
. ,...4...m_...
. . . . .. . y ..e..,,...4 .
reduced to ncminal cperating pressure (-0.1 to + 0.3 F3ID), reset containment spray. Spray pumps should be shutoff and placed in the standby mode with operable flev paths.
e v.
u"u s +o y. . . ""'v-- +.o c - ^. i .a.3 ..r. ." a..n d. ." a. ul...v
~
a + d . . ..s u^ a , .- a. .e, e +. s a" - . a. .~g . ' .nv' e a 'v '.. .". , 1 ". .n .- *.
previously reset.
cn..r+.
v ~ v... T .o b '.a. a. b. . w -".+. ma.".s a#+a.= . . . .
e svi+. a .k..d..s . .r t o *. h a. ". a. c .4 .- ul aw.+ 1 ^. n ~- o d e ,
e see LOeA- B .
SQNP (p ,
E01-1A - Units 1 and 2 P ! . . _ " '" ?
Page 8 of 15 .' -
Rev. 10 '~"-\u ,
II. SUBSEQUENT OPERATOR ACTICNS (Cont.)
T. The following automatic phase of switch-over from the injection to the recirculation mode is initiated when the REST is at low level ~ 29%
(120,000 gal) coincident with a containment sump level of ~ 10%
NOTE: The times provided at the end of subsequent steps are normal times for the valves to travel full stroke.
NOTE: All operator actions must be performed expeditiously, in a precise, orderly sequence. Do not interrupt the changeover cperation until all actions are completed. If a valve fails to respond or to complete its demanded operation, postpone any corrective actions until the subsequent steps are performed except as noted. Loss of one complete train of power will allow the other train to be swapped, and parallel valves required to be closed will require one valve to be closed locally, see Appendix F for contingency actions. I
- 1. Verify that valves FCV-63-72 (A-A) and FCV-63-73 (B-B) RHR pumps suction from containment sump, start to open while RER pumps continue to run. (2 min) 1 CAUTION: If a containment sump valve cannot be opened, stop the corresponding RHR pump. ;
U. The following manual operations are done upon verification that the automatic switchuver phase has begun.
CAUTION: Immediately stop any pumps taking suction from the RWST on indication of the RWST being empty. Complete the switchover steps listed below, then restart required pumps.
- 1. ' Close the following RER HX outlet crosstie valves.
- a. Close FCV-74-33 (40 see)
~
- b. Close FCV-74-35 (40 sec)
- 2. Open the following component cooling valves: (Panel.'!-27B)
- a. Open FCV-70-156 FOUL HX A outlet (60 see)
- b. Open FCV-70-153 PJ01 HX, B outlet (60 see) t 9
~'
SQNp .. .
E0I-1A - Units 1 and 2 -
Page 9 of 15 L Rev. 10 II. SUBSEOUENT OPERATOR ACTIONS (Cont.)
- 3. Verify flow to the RCS from the safety injection pumps and close the following SI pump miniflow valves:
CAUTION. Repressurination of the RCS following performance of the following steps may cause damage to the SI pumps if pumps are not removed from service og provided with an adequate flow path (maintain RCS pressure less than SI pump shutoff head for adequate flow path).
- a. Close FCV-63-4 SI pump A-A miniflow (10 sec)
- b. Close FCV-63-175 SI pump B-B miniflow (10 sec.)
- 4. Verify that the automatic valve realignments in step T above have been completed.
- 5. Open the following:
- a. __ Open FCV-63-8 RHR HX A outlet to centrifugal charging pumps suction and SI pump A suction (10 see)
NOTE: 480V breaker must be closed before operating valve from control room (Rx MOV bd Al-A)
- 7. Open the following parallel valves:
~
- 8. After completion of the above steps verify that the two SI pumps and centrifugal charging pumps are receiving suction supply flow from the RHR pump, and proper flow is estab-lished to RCS cold legs on all injection pumps.
CAUTION: Do not perform steps 9 and 10 until the above verifica-tion is made.
SQNP E0I-1A - Units 1 and 2 Page 10 of 15 Fev. 10 II. SUBSEQUENT OPERATOR ACTIONS (continued)
- 9. Close FCV-63-5 safety injection pump suction f rom RWST (2 min)
- 10. Close the following: i I
- b. Close FCV-62-136 RWST to centrifugal charging pump suction (10 see)
- 11. Periodically check auxiliary building area radiation monitors for detection of leakage from ECCS during recirculation. If significant leakage has been identified in the ECCS, attempt to isolate the leakage. The recirculation flow to the RCS must be maintained at all times.
- 12. While the plant is in cold leg recirculation mode, make provisions for an evaluation of equipment in the plant if not previously done.
Request sample of recirculation sump and adjust sump PH if required.
V. After going into the recirculation mode, the containment spray pumps will continue using water from the RWST. Upon reaching the RWST low-low level alarm point (di 8% = 50,000 gallons), as indicated on the qualified, PAM indicator channels, realign the Containment Spray System. The following steps are required for the realignment of the Containment Spray System from the injection to the recirculation mode.
- 1. Stop both containment spray pumps (CSP) (" pull to lock in stop" to preclude the possibility of pump restart while realigning suction valves).
- 2. Close the following valves:
- a. Close FCV-72-22 containment spray pump A-A suction from RUST (1 minute) l 1
- b. Close FCV-72-21 containment spray pump B-B suction frcm RWST (1 minute)
SQNP E0I-1A - Units 1 and 2 ,
Page 11 of 15 Rev. 10 II. SUBSEQlIENT OPERATOR ACTIONS (continued)
- 4. Open the following CSP suction valves:
- a. Open FCV-72-23 containment spray pump A-A suction from containment sump (1 min)
- b. Open FCV-72-20 containment spray pump B-B suction from containment sump (1 min)
CAUTION: If the pump suction valve from sump or the RHR contain-ment sump valve will not open, i,a t rec art the I l
corresponding contain::: ant ap.. ,
- 6. Start containment spray pump A-A (HS-72-27A)
- 7. Start containment spray pump B-B (HS-72-10A)
- 8. Verify at least 4500 gpm flow on CSP A-A (FI-72-34)
- 9. Verify at least 4500 gpm flow on CSP B-B (FI-72-13)
- 10. After completing the preceding steps, verify that the safety injection system is aligned for cold leg recirculation per Appendix E.
CAUTION- DO NOT remove either of the EGTS trains from service until recovery from the accident is p?anned. Flow switch problem may prevent restart of equipment.
W. Thirty minutes or longer after the accident occurs, place one of the operating auxiliary building gas treatment systems in standby cperation according to SOI-30.6.
X. After E 15 minutes (sooner if possible) stop the emergency diesel gen-erators if off site power has not been interrupted, and prepare for restart.
Y. Approximately two (2) hours after a design basis accident, the ice in the ice condenser will be depleted. At this time, containment pressure will increase and if containment pressure increases to 9.5 psig, place one train of RHR in containment spray mode.
1 1
e ,.
- s. t ,
- r. n.T. _ ,. .a.
. n.
s 4. .+. e ,. , . a. o
..s I sp*
r age le^ o.p le t n.e..
. . . o i
y1. e.
< r.~e rn,+ .r". .i m c o. - .n. .,a r,n. .n m. - [ c c n..+ 4. r..,Le a
... ~p w.1a*
. )
e s . . u. .s m. ,. . o r 0 . o. . .,. ., +* a .' ~....a."su' .-a d o a .r, ~u k .' .' o-".
+
_. mus..... . . I.'.'.. . o . . '. a 4. r..
. . . ,. . ~+ .c.. .- _a .',r I ficv on train A or 3:
",.,,,.4.,.. " ..f 1 " ,en.c
. - ._. .. .. e,,
...,,4.. ....,.c.,
4 , , 4 ,
. . . . . .4. ..,.
1 l
i 1.
close the n:..-n ec d ;,.es isolat,cn valve rv,.,.-e2-ya.
l
- 2. Cpen the HER containment spray header isolation valve
~ . , .n.9 - ,., n rv. v.
pg . ff e tt m.-
irain a nnn conta.gn=ent spray in t4.ation.
- 1. Cloce the EHR cold leg isolation valve FCV-63-9h.
- 2. Caen the RER centainment spray header isolation valve ruv- g bi.
1 4
AA. Approximately 15 hours1.736111e-4 days <br />0.00417 hours <br />2.480159e-5 weeks <br />5.7075e-6 months <br /> after transferring to cold les recirculation, realign ene train of ECCS fcr het leg recirculation to accure a._ ainst an
. . . .4..m. s , 4
. . -_, 4 . . ,.#
w - ,...4 ,, .. , 4 2 .....,s.<,...
.. ~...
. . . 4 .. , ,. . - , . , .
'- +
C A.". .' ~. ^ .". n.
. a,. ~ y- e s .m.d % _' a. ."-.4*.'.,..
4 .". ...a. # +'"
v^ .' .PCV ~I
......",,,,",',..a.m.
<. . . ...e ~ --
,"4,.4.., .,.,,;,
a,...,,...,......-...o .w4- w w _o_.. L ". ; =
- d
..4 .. .. . . . _ . , . . m. 2 c m ,.21 . m m. . .a . uce . 4 na. .: .t. , .oo h e- ., 1 e, . 44.c,,..,
4
, s . . . .. v n. %v. ,,,,4.. . . - .
. . . . - p m nnn .or hot leg rec rcu3at.4cn 4
. on.3.y 4.n extreme emergency. .nn.ae 4
Train A RHR is in het leg recirculation, leave Train 3 RHR in cold leg recirculation.
- 1. Train A RER Changeover to H.L. Recirculation (Freferred)
- a. Close FC"-63-93, R .R pump A-A cold leg iscit. tion valve
'o . Open FCV-TL-33, crosstie isolation valve between discharge lines of RER heat exchanger
- c. Open FCV-63-172, RFR pump H. L. isolation valve
- d. _ Verify H. L. flev en FI-63-173
%.s
, , - , n, ..c ,
cw%v..m.
E0I-1A - Unit.s 1 and 2 Fage 13 of /d -
Rev. 10 e.m-,
T.
.. a n r .,,umo
_ ~,Lm. ,,..v . .,, R x, C,_,u.. ... ( c o n.. i. n , e l. ;
- 2. Train : nna changeover to ' L. Eecirculation (Used Cnly if Train A Cannot be Used)
- n. Close FCV-63 ch, RER pump E-3 C.1. isolatien valve o
.c. Open ru --.l ,,4-d;, c , . . - - ,
r.nr. pump s-s crosstie valve
- c. If not open, open FCV-63-172, RHR pump H. L. isolation valve
- d. Verify H.L. flov en FI-63-173
- 3. Realign the safety injection pumps to deliver through the hot leg injection headers to the reactor coolant system.
- a. Stop A-A safety injection puaL.
u.
v c,0se v2 sv-,v-os pc,, sa,ety ,n,ect.;on
. o pump a. ,
n crosstir 1:01ation valve
- c. Open FCV-63-156, safety injection pump A-A hot leg isolation valve
- d. Start safety injecticn pump A-A and verify flev to the ECS through the het leg header. (FI-63-151)
- e. Stop B-B safety injection pump
- f. Close FC-63-153, safety injectica pump 3-3 crosstie isolation valve
- g. Open FCV-63-157, safety injection pump B-B hot leg isolation valve
- h. Start safety injection pump E-B and verify fiev te the RCS through the hot leg header. (FI-63-20)
J. Close SIS pump isolation valve FCV-63-22 vith HS-63-22A
.g'-1.
l l
o -..
c.3 .
. ~..
EOI-1A - Units 1 and 2 ~-
r
- abw *h
-a ' ^* *" '* /t
- Rev. 10 "- -
- y. ,1. -...,-.~,.u wron .
t-p-nA z w,,n c.C s m. .o
,- (cona.nued)
- 33. Stop the containment spray pump when determined that the containment pressure will stay below 0.25 psig, if not previously done, reset phase "3" and place Opray pumps in standby with operable flow path.
CO. 1. place one train of H, recombiners in service per 30I-33.1 if contain-ment H concentration reaches is by volume, but no later than 2L hours after!heaccidenttoencureamixtureoflessthanChhoursafterthe accident to ensure a mixture of less than h5, ty volume, in contain-ment. Place the other train of H recombiner in service if contain-ment 3,concentrati0n reaches 13 57 volume.
Each recombiner is rated s 75 Kw maximum capacity. If diecel gener-ators are carryir.g the electrical load, do not exceed h000 Kw continuously or h400 Kv for a tuo hour period. If maximum lead cn diesel generators will be reached, notify SRO and make evaluation en which equipment may be safely removed from diesel generator load so as to allev loading of recembincro.
- 2. Monitor the containment H, sus monitor and once per shift have the cent 2inment air campled and in the event centainment at= sphere reaches 35 H,, by volume, the H2 purge sycten vill also be pinced in service per 50I-S3.1.
UCTE: Sample frequency may be changed based en rate Of change of H
2 oncentrati and radiation dose received drawing sample.
1 3 Keep containment air return fans in service for duration of H, buildup problem.
DD. Guidelinec for removing H, and other non-condensables frcr the primary system i. hen trapped and cannet escape to c;n;ainment, Keep primary ejster pressure as high as possible to prevent bubble i
- 1. '
from enlarging and also to entrain more non-condensables in the react or "aclant unter.
6 O
6 4 .
t I
i
E0I-1A - Units 1 and 2
- ~ ' _
Page 15 of 15 Rev. 10 II. SUBSEQUENT OPERATOR ACTIONS (continued)
- 2. With Phase "B" isolation reset and RCP's operating (RCP #1 or 2), P2R heaters operable, use spray valves periodically to strip non-condensables from water to PZR vapor space. Then open PZR PORV momentarily to vent non-condensables to PRT where it can be vented to waste gas system or to containment if RPT rupture disc is blown. With RCP's not operable, Au>:iliary spray may be used for stripping non-condensables.
- 3. If normal CVCS letdown can be accomplished, non-condensables can be stripped in VCT vapor space and then vented to waste gas system and stored in waste gas decay tanks.
CAUTION. If this method is used, monitor CVCS system closely for leakage and set up proper radiation protection measures.
- 4. After careful consideration, if it is decided that it is desirable to burp non-condensables from the upper head area, a slow (s 10 psig/
min) controlled depressurization can be utilized to gradually burp non-condensables into #2 hot leg from the vessel upper head into PZR surge line where it can be vented to the PRT.
CAUTION: If RCP cavitation occurs, trip RCP's.
CAUTION: If during controlled depressurization flow blockage occurs I as indicated by increasing t:mperature of RCS, re pressurize I and establish flow. {
III. RECOVERY '
The reactor will remain in recirculation mode for an indefinite period of time.
Instructions for recovery shall be prepared when the condition of the contain-ment and the accident evaluation is determined. ,
1 1
IV. REFERENCES FSAR 15.31 6.3
- i
. . ~. - , - - . Son.o
+
' ' ^ - ~
"~ E0I Unita 1 and 2
.';.' ' Pace 1 of 5 s[J - . . . u Rev. 10 '
,,,.,.,,,m .,,-r s . n u w m sv..n. . , , . ,
a . e ,. ,,
.u . a 0.0 n;se.
--,.,me,.....
v....-..s n uvus .4 nr.~_ c. v . u v.. ...v
--,..c........ . ., a I. ,...,- . ..,r i wa 0:
A. Loss of ncr al contr01 rocm lights and e=crgency lightc cn.
a . ,oca n
of a..ti loads ccnnected to . s..e c.y,,c,, an:. 4cv .., unit smoaru, anc o.r-se.
in, . . - .
and h80-V shutdo'.in board.
C. "6900-7 unit board 1A (13, 10, and 1D) (2A, 23, 20, and 2D) failure or undervoltage." (Setpoint 68 percent of normal voltage after 5 secends tine delay.)
D. "h30-V unit board 1A (13) (2A and 23) undervaltsge er trancfer."
(Setpoint 68 percent of nornal voltage after 5 seconds time delay. )
E. "6900-V SD 3 card 1A-A (13-3) (2A-A and 23-3) failure or undervoltste." )
(Setpoint kl percent of normal voltage after 1.5 cecends time delay.) ;
F. "hcO-V SD Board 1Al-A (1A2-A and 231-3 and 132-B) (2Al-A, 2A2-A, 231-3, and 232-3) failure er undervoltage." (Setpcint 63 percent of ner:a1 vcitage after 2 seconds time delay. )
O. "6?00-7 : tart bu: failure or undervelta e" on contr:1 building rec;rding l annunciator. (Setpoint 79 percent of normal voltage after 2 se:cnds '4 a delay.)
II. AUTOMATIC ACTION A. Diecel generators lA-A,13-3, 2A-A, and 23-B start and cloce en their respective 6900-V shutdcwn board for beards that lost voltage.
- 3. Blackout sequence initiated for boards that lost voltage.
11.. v. . .. . ,u n .r ay D~r .f.w
. . - crm.w..
n: . ce r r.
n- J A. If a station blackout happens after the LOCA when the emergency core cooling system is in the sump recirculation mode and the SIS has been reset, proceed as follows (only for the unit which has the LOCA):
CAUTION: Do not reinctate the SIS, ac thic vould cause manually repcsi-tiened valves or other equipment to go to the condition for the post LOCA recirculation mode.
- 1. Verify that the diesel generators close in on the 6900V shutdown boards and the " Blackout Sequencer" starts sequencin6 loads for boards that lost voltage.
- 2. Lockout centrifugal charging pumps prior to (preferred) or just after they start to prevent pump cavitation until RHR pumps are restarted.
. ., ,-[
A
" . " ~ ' ' ~.
- ~ - -
3 ns.u.n.
1 e
T.~O T_ ,,, 'I.D. ,
I.f.e. ..
J . e.> 1 e n. . l m9
- g -4 ,
C =: L... ,t, g Fage 2 of 5 Rev. 10
.. .. . v... ,r.in.
.J - . ce.
L ~~.,a u .,. .
n r*.c......-
.L rg ,J.. .*a-t -
4 ...m p/
_s . 6ecure tne .pressuricer neaters (au) ,. fo.. to trevent over oaca nc :ne diesel generators,
- b. Start centrcl air ecmprescor: A and B iccally.
- 5. hatch diecal leads c10sely. Start the following ac caen ac posuible without overicading the diesel cenerators. If diesel loads get excessive, secure equipment in subcequent actienc :tep A.1 belcw before ctarting additional equipment.
e
-. v...=.=.r.....,,
- b. Centrifucal charginc pumps
)
- c. SIE pumps A.
- C o . . '. a. .' .. ... . .* e ~y"". a .". y~.~y /w. ~.*. a 4-.
~
~. ..*. ,~. ~. .~. ~. e s o. . . . D .' . .- < , )
- c. Containment air return fans if not running, and d 3 has initisted.
- c. Anncunce black 0ut en FA cystem.
,, c ,=nc_~.,,~.,.,. e - - e wn,, e s , e . ~ .n e. =. .=w. r c o. :~.e - -
A. 1. For the unit which underwent the LCCA, secure the following icade OFF: (this is dcne +o avoid later overloading the dieselc) 1 1
1 (a) Reactor 10wer cc partment fans. ;
N 0'"E : Will not ccce en if $ 3 is not reset.
(b) Control rod drive mechanism coole fans.
1 1
NOTE: Will not come en if QB is not reset.
(c) Boric acid transfer pumps.
- 2. The following loads are fed from the diesel generators. Start equipment as necessary to reestablish operatien of safety equipment
+"a* va ce- .. .+.4. .e~ r"*4. c-. . . + o kl- a - c r.~~.+ .
...o. m. . ,,.. .. . %. . .< ... _ , .c..1,.
.e
- a. 3 .,,, --- ... . u... 3
, ~ .,-. ,. .
. w.__.
. . .. ,v - . .,.J-Ew con.inuously rnu e tw . a a n.= perica. Ir nr.ximum load limits become a problem, notify SRO and decide which components may be removed from service safely.
I
-\y. .e e
.- ,, , .,. . . . _ . . , . . . . . . . . - __ m - . . , - _ -.
4 ggp E0I Units 1 and 2 ru. . ._, . Fase 3 of 5 Rev. 10 1u, e_n c =,. r=.n.m. ev. .=.v ny. e o. . ,~---
_-..n.q n.
c /s,, ) r., . . . ,
_ ..y
.,- e.,.,
2#
.,....3..,.
(b) Cc : trol building pressure fan, if not running (c) v. ,. 4 -5...
. - _, ,. . ,.e
. . . w 4 ., . ( u.,
W si env_^2.,
. L
- c. I B. The following loads are fed from the diesel ceneraters. Verify equipment operating or start as necessary to reectablich pre-blachcut conditienc :
- t. g +..,, w. . . .~ ., , a- ,
sc
, 1
.u.- n~.
- . = . ~ .,.-o... .r . ;
- 1. Essential raw cooling vater pumps j l
- 2. Cerpenent ecoling water pumps j 3 Containment sprcy purpc L. Centrol building nain centrol room condensing unit
- 5. Centrol building electric board room eendensing unit
- c. Auxiliary centr:1 air compresser 7 Ccnt ainment air return fans
- 8. n..u.p y ., yA.e. .t I
9 Vent radiatien monitor
- 10. Spent fuel pit cooling pump
- 11. 125-V Vital Battery Chargers ,
i
- 12. Emergency lighting cabinet I 1
i I
13 Fuel handling area exhaust fan (after L hourc) lb. Shut devn board room air conditione" chiller
, 15 Shut down board room elev. 73h AHU
- 16. Electric board room AHU 17 Radiation monitor and sampling
i' l
- 20. Control room air conditioner AHU '
'l
-tC- l ,
O'9ee4 m.
h, r--~ y~ n..' .
.7 E01-1B - Unita 1 and 2
- 2. . page h of 5 tl t.- . . : . '. Bev. 10 L.S. !a a r t.. v L
- u. e . . r ~ ..,.
v u .w v .. . . Cr. ro. .n . nv.n, , . r n..,, L,, c.
m
- .c 4 ,,e a. )
..~.~
- 21. C:ntainment cpray p=p IJ~J
- 22. F1pe chase AHU 23 Fenetration rooms el. 669, el 690, cl. 7.'.h /dU's 2h. Aur.iliary feedvater pumps 25 Shutdown transformer exhaust fans
- 26. Control building cleanup fans 27 Elev. Th9 board room pressure supply fans i
- 08. Elev. 749 board room AHU's l i
29 Elev. 7L9 board room condenser units
- 30. Elev. Th9 board room compreccors
- 31. Control building battery room elev. 669 exhauct fans
- 32. Emer;;ency gas treatment fans and heaters
- 33. A a.iliary building gas treatment fans and heaters 3h. Emergency 6as treatment room AHU l
- 35. CCS and Ard /diU 1
- 36. Shutd:e. board rec = air cenditioner prescure fan 1 37 Station air compressor
- 38. Control building pressure fans 39 Shutdown board room air conditioner CW pump LO. Eccential raw cooling sater strainer bl. Hydro;en recembiner
- 42. Isric acid transfer pump 43 Boric acid tank heater hh. Motor operated valves h5 Charging pump auxiliary oil pump r0 7
gQNp E0I-1B - Units 1 and 2 Page 5 of 5 Rev. 10 IV. SUBSEQUENT OPERATOR ACTIONS (Continued) 46, 24 volt microwave battery charger
- 47. Diesel starting air compressor
- 48. Diesel battery board exhaust fan
- 49. Diesel building exhaust fans
- 50. Diesel building fuel oil transfer pump
- 51. Diesel building lighting cabinet
- 52. 125-volt battery charger '
- 53. Diesel engine day tank fuel transfer pump
- 54. AERCW pump statica trace heating cabinet
- 55. Room exhaust fan
- 56. ERCW pump station fan and heater ,
l
- 57. ERCW traveling screen and wash pump ,
l
- 58. Spent fuel pit pump AlrU i 1
- 59. Diesel building electric heat 1 l
- 60. PZR heaters l
l V. RECOVERY j
Once the required electrical loads are restarted to establish preblackout conditions, continue RCS cooldown in accordance with E01-1A.
VI. REFERENCES FSAR 6.3
4 s
e 6 00lW PO'~9 ww ~v..J.+>
f t.
s .
9 ,, 6 4 O
-sa -
Appendix A
. Page 1 of 1 P.e'/ . 10
~
l SATJPAT ::I STEA:4 TABLE
(~emperat.ures rour.aea to nearest F) l sat. 50 F sat. 50 F l Fe 3 Terr ? sub r ele-1 Ps:0 Temn = 21:2 2:le-2 200 L22 372 1250 56h 52h 350 h36 356 1h00 588 538 l
koo kh8 395 1h50 593 5k3 l h50 h59 h09 1500 597 5hi 5CO h70 L20 1550 602 552 1
550 h80 h30 1600 606 556 1 600 hS9 b39 1650 610 560 650 h97 Lh7 1700 61h 56h 1
700 505 h55 1750 618 500 '
750 513 h63 1800 622 572 800 520 h70 1850 626 576 850 527 L77 1900 630 530 900 53h h3h 1950 d33 553 950 Sho L90 2000 637- 557 1000 Sh6 hg6 2050 6h0 590 1050 552 502 2100 6hh 59h 1100 558 508 2150 6kT 597 1150 563 513 2200 650 600 1200 569 519 2235 653 603 1250 57h 52h 2250 65h 60h 1300 579 529 Saturation temperatures may be read from hot leg temperature F,TD'c or incore T/C's.
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?:3 Etr's available as follows:
1A-A: 1) .hnual cperatica allovel i=.ediately folicwing CI so )' .A u* o ay~ ~.a. . . d. ~.1 --"ovad-* C,O , .**+^. .#..'.'ad.,
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- 3) I4anual operation allowed 30 sec. fc.,11:ving 50 and Z:
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.. .m...
- 3) I4 nual operation allowed 90 sec. folleving 30 and 3:
IC: 1) Manual / auto operation alleved folleving 30 by resetting 30 signal.
1 i
1D: 1) Ihnual/ auto operation allowed fo_ lowing 30 by resetting PO signal,
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bd 1 - Units 1 and 2
-- ~ ' , Ar.t'endix C v , ,, n. _ o.e 1
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A. The following are cuidelines to determine if natural circulation is i 9.inc place
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- 1. Core $ T as read on wide range RTI's (hot and cold) cr an indicated 4 T between W.R. cold leg and incere T/C's should te stable or droppinc. A relatively stable e T with values less than 55 F with a gradual decrease indicates natural circulation.
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existing primary system pressure.
l Heat is being removed from the primary systen by secondary system, i.e. ,
l 3 '
S/G's steaming and water being added to S/G's and secondary system pressure near saturation for the primary system temperature.
i
- 3. l The following are guidelines to enhance natural circulation. 1
)
- 1. Keep 3/G 1evcis in narrow range (tubes covered), between LO% and 715 for '
post accident instr =ent error. j 1
- 2. I:eep primary systen pressure above saturatien pressure for the existing '
het les (W.E.) temperature or incore T/C temperature if possible.
- 3. Use cendenser steam dump or S/G FORV's to stea.m off and cool primary systen at desired rate.
C A'.'T! ?" : "f ster. iump is nece :ary, reduce the S/G pressure to 86L psig
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unintain a reacter coolant coc1down rate of no more than 50*F/
HR, consistent with plant makeup capability.
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E0I-l - Units 1 and 2
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- - - Au..cendix 3 Face 1 of 1 Rev. 10 2..c.nu ..c 22u...,
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To specify precsuticns and operstion actions ained 2t restcring a ecnliticn of ccre ecoling during a 3:211 LOCA.
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- 1. Throughout this instruction, continue efforts to provide safety injection and/cr charging flow to the RCS and/or feedva+.er flev tc the S/G'c.
Att empt to oper9te equipment n.snually locally, if pessible. -
- 2. Ccntinue monitor.n; cf ccre exit thermocouples to determine effectiveness of cubsequent a:-
- 3. ' epressurize the RC3 by i
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-T .c +w..o. .e. .a.m. .. c e ..4 - .30 . au. .,. 4 3 .,.w. ., .n. , af e,+ e , . + wm ,.m..,
. .w. + w..
.m . .w. e.e
, . .., , l relief valves, or, CAUTION: Depressurination through use of the S/O's should only be attencted if there is an effective water level and auxiliary or main feedvater is available.
- c. Open the PZR FORV's only if: I
- 1. SIS or charging is available to deliver to the ROS,
- 2. RCS depressuri;ation cannct be accomplished by steam relief frcm the S/G's.
- 3. Feedvater is not available to maintain the steam generator secondary water level at an effective level.
- k. If no means for RCS depressurination are available, or if the deprecsuriza-tion did not result in decreasing core exit thermocouple temperatures ,
then start a reactor coolant pump, if possible.
CAUTIO3: During the conduct of this instructi0n, the RUST level should l
I be monitored for switchover to ecld leg recirculation, if required.
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i e p! nppenaix t, l ni Page 1 of 1
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COLD LEG RECIRCULATIC'I VERIFIcA7:en A. One RHR Fump is delivering from the centai=ent recirculatien s=p iirectly to two reactor ecclant system cold legs and tc the sucticn of one SI p=p and ene centrifucal charring p=p.
- 3. The other EHE Fump is delivering from the contai = ent recirculation r=p directly to two reactor coolant system ccid legs and to the suction of one SI pump and one centrifugal charging pu~p.
C. The two 3I p eps and two centrifugal char 6ing pumps are ta?.ing suction from the RHR pumps and are delivering to four reactor coolant system ccid legs.
D. The suction paths from the EWST to all safety injection p=pc have been icolated.
E. If centainment spray is required, verify that flow is being delivered.
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E0I Units 1 and 2 Appendix F Page 1 of 1 Rev. 10 r.. n. ". ors . . . , -., , Cy >g~ em.. T. c.,. ;.e.
- 1. Cantainment Eecirculation Sunn "alve Failc to Cren If a containi.cnt recirculaticn sump valve cannot be cpened, et:p the ccrres-pending RER pt=p and verify that :
A. One RER pump is delivering ficv to two reactor coolant system cold legs and to the cuction of two SI pumps and two centrifugal charging pumps.
S. The two S! purp and the two contrifugal charging pumps are delivering to fcur reacter coolant cystem cold legs.
- 2. Loss of One Train of Electrical power A. If the single e:+'- ~
1 >
- ' cne of the emer;ency diesel genera;... ., . . . _ . . , '. unction with a LOCA and a loss of offsite power, electrien1 power vould net be available to one Of the vital cafe-guard busses. As a consequence, all engineered safeguards equipment assigned to that corresponding electrical power train vould not be avail-able for operation until power could be rectored to that buc. The inctruction fer evitchever to ec1d leg recirculation, accuming a train failure, is eccentially the came as the instruction which acsumed no single failures.
Follow the no cinc2 e failures instruction ctarting with ster T, with the understanding that those valvec, without power, do not have to be repositioned.
It should be noted that if a train failed subsequent to the initiation of the SI signal additional steps may be required. For example, if no failure is acsured, the parallel suction valves in the line from the RWST to the charging pump suction header would open on an SI signal. Should a subse- -
quent failure of one of the electrical trains cccur, one of the parallel suction valves could not be closed frc the main control rocr. Therefore, pocitive isolation of the RWST to charging pump suction path would have to be accompliched locally.
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- 2. Verif.v sa'ety . inl.ection pump avail.bilit~..
3 Verify EER pump availability
- b. Ve...* * *2 y r *. "_ i. "a.' ' *. L e n v. _ do b.= " ^. = .~
- - - a.6-' ~ . ~ ' . ." . ~ - ~~~..1.*..'.'.*.*..~,
5 Verify containment vent icolation equipment availability c' . u. ...
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- 11. Verify RCP availability.
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- 11. . Verify containment cpray equipment availability,
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- 16. Requect campling of RCS for:
- 1. Eoren concentratien
- b. Fuel damace
- c. D. E P
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