ML20091L782
| ML20091L782 | |
| Person / Time | |
|---|---|
| Site: | Vogtle  |
| Issue date: | 06/07/1988 |
| From: | GEORGIA POWER CO. |
| To: | |
| Shared Package | |
| ML20091B437 | List: |
| References | |
| 49006-C, NUDOCS 9201280236 | |
| Download: ML20091L782 (36) | |
Text
_
r i
, O 73M Unit _ COMMON Gec)glaPc))ver
- e. 4 3 -
%fw ;
y; . , . . .
'I ;
HEA1.TH PHYSICS AND CHEMISTRY IMPLEMEhTING PROGADURE DEPARTMENT _ OUTAG ", j
.. i 1.0 _ PURPOSE .O
~s 1.1 This procedure identifies the Chemistry outage activities to chemically treat and layup systems, identifies the Health Physics outage activities to reduce radio activity levels in Plant systams and reduce exposure to personnel during an outage, describes the support necessary to complete them and defines the responsibilities for providing suppor,t.
NOTE Outage Types are describsd in Procedure 01000-C, "Maangement Of Outages". 4 1.2 This procedure applies to Type IV Extended forced
_0utanes and Type V - Scheduled outages, depending upon the duration and plant configuration. If e, _II -
Svatem Outage, and g III = Short Forced ug - turn into g e applicaole. - IV outages. this procedure will be 1.3 Durina shutdowns and startups for outages, chemical specifications change. The cleanup or layup of plant -
involved can not be securst: systems may require holds where the pla 1 procedure names that plant equipment.Where possible this, 1' 2.0 F DEFINITIONS " '. -
2.1 ACTION P!ANS = Written outline of actions to be taken and the department responsible for their completion. V' 2.2 STRtJCTURED BRIEFINGS - Briefings or action plans w conducted by Chemistry for departmental personnel and .:
representatives of all other responsible departments. -
9201200236 911231 DR ADOCK0500g4
= =
.. n . . ,
lp emocso n ca
, g.
. . ~ - .
...e w m1nl & @ @ M,!':WNW$
nsym on..,. g. PAosNo,c.,,s . . . . g. . .
(+ 49006-C N,. '"
- W 7 VEGP - . n
, .7;,g33,.,;;
%.0 c 9,i ,
p,W
'%0 '
2.of$6'.!guJ/. '{
-[ .... -- , , ' ,,c. l. [
'e 2.3 CHEMISTRY OUTAGE PLAN Outage Activities develo Outline of Chemistry Deaartment 7. 2 Technical!Suppore Group.. ped e.. : and maintained by C2emistry..
.. . .p . .
.... ., M;4 :M ...A.. ..-
' 2.4 .
s CHZMISTRY RITENDED LIFE AND. PLANT LAY-UP HANUAL 4 - i actions of Balance of Plant r Manual'for,
- I.* *.*** *. ?.ANQj; @l Lay-upandinspISNi
' U*': ;
a RESPONSIBILITIFf ,'5,:. R. . t .
3.0 . .
?.g-3.1 7 MANAGER-HEALTH PHYSICS / CHEMISTRY p .:
The Manager-Realth Physics / Chemistry is responsible for the management of all aspects of the Chemistry Section.
Health Physics Section arid MP/ Chemistry Support Section activities during an outage.
3.2 SUPERINTENDENT OF CHEMISTRY 3.2.1 Give direction to chemistry department personnel and the Chemistry Outage Coordinator during outages. '.. -
3.2.2 Direct the development of the Chemistry Operations '
section of the Chemistry Outage Plan.
3.2.3 Review Chemistry data and request corrective actions as !
necessary.
1 l 3.2.4 Maintain adequate supplies of layup and RCS cleanup chemicals..
3.3 SUPERINTENDENT OF HEALTH PHYSICS AND CHEMISTRY '
TECHNICAL SUPPORT 3.3.1 Give direction to the Technical Support Group' Personnel and the Chemistry Outage Coordinator.
1 3.3.2 Direct the development of the Chemistry Technical S Support's Outage Plan.' outage activities section of the Chemistry .
3.3.3 Provide Technical Support to Chemistry Outage '
activities. l 3.3.4 Assign a chemistry Outage Coordinator from the i Technical Support Group.
Q i
70WS .
mwas No. ~""* -
'navymon.,
x
.g a, z:cRcW.?; 'C'" W Y VEGP 49006;ce ,,.g:lu.t0 .1 ggirg,y' a no. ; g._
.s.. 2
.. . .N-i,wp -
3 of"36 '. ' . ;,z
- c . . . . . . -
3.4 }
CHEMISTRY. TECHNICAL SUPPORT' GROUP OUTAGE']. C 3.4.1 Develop the Outage Chemistry Plan. y~
3.4.2 ..
about chemistry outage activities. Provide information T u . ..
.. . ~n 3.4.3 . . . . ,
Track Maintenance Work Orders written to perform . ..
Teclmical Support Group Engineers.inslections andll,cor
.):
3.4.4 Attend. outage plannin u' chemistry activities.g meetings and provide status of '.
3.4.5 Attend Plan of the Day meetings with Work Planning.
3.5 CHEMISTRY TECHNICAL GROUP ENGINEERS
3.5.1 Identify inspections and corrective maintenance for outage on systems to which they are assigned. '
3.5.2 .
Write Ma'itanance Work orders to perform inspection and $-
corrective maintenance.
3.5.3 Perform inspections as necessary.
3.6 CHEMISTRY SUPERVISOR-SHIFT OPERATIONS '
3.6.1 .
?
Provide-technical expertise and direction for personnel in the Chemistry Operations Section during outagee. 4 3.6.2 ProvideothEnizationofIctivities.' technical 'I direction,And assignment of work tasks to implement the Chemistry Program during outages.
3.6.3 .
Schedule qualified personnel in Chemistry Operations Section to suppor. outage activities. M.
3.6.4 Review schedulerequestsforsupportduringoutages. schedule .4 '
3.7 CHEMISTRY SUPERVISOR-SUPPORT a 3.7.1
,4.,
Provida technical expertise-and direction for personnel t in the Chemistry Section Support group during outages.
(
I i
rows . . "'.
J ~
t 3.7.2 Provide organization of ac'tivities, technical direction and assignment of work tasks to im [.s' the Chemis,try Support Program during outages.plement ,
3.7.3 Schedule qualified specialists as necessary to support -
outage activities.
3.7.4 .
Provide specialists for technical assistance when '
requested in support of outsgo activities.
3.8 CHEMISTRY FOREMAN 3.8.1 Direct the activities of the Nuclear Chemistry Technicians during outages. including activities in the laboratory 3.8.2 Review che-totty data of all analyses performed by correlations for any abnormalities, and init conduct NuclearChemistryTechniciansdurangoutageslate corrective actions for out=of limit conditions.
3.8.3 Ensure all shift activities during an outage are conducted in accordance with technical specifications and the latest revision of approved procedures and standing ordera.
3.9 CHEMISTRY TECHNICAL SPgCIA1.ISTS 3.9.1 Provide technical assistance and support outage activities when directed to do so by Chemistry Supervisor Support. -
3.10 HUCLFAR CHEMISTRY TECHNICIANS 3.10.1 Perform sampling and analysis of plant systems and components during outages in accordance with technical ,
specifications and the latest revisions of Chemistry procedures.
3.10.2 Perform chemical additions in accordance with Chemistry proceduras. I 3.10.3 Review data for accuracy and identify and raport out-of limit r:onditions to Chemistry Foreman on shift.
.~
.~. _- - ..
a, s . - .ggggl y,,
w;' . pnocaouns mo, g,w
, gt.;g,ig. , ,
.s . . , . . "', , , , no, VEGP 49006 0 ' '. i
'O
. 5 of 38 h l 4.0 ., .
TYPE I!! = SHORT FORCID OUTAGE BY NODES i, [
4.1 MODE 3 ot 4 '
- p
- .i NOTE. k4.i..g;'. ?'.. N
., I' k When the Reactor Coolant Systen t ~;g 350 Ferature the solubility of is decreased below activa,ted corrosion products lq%-
(CRUD 3
in a ") Crud Burst". theincreases which results:
purification flow rate should be maximised and any draining from '
- the Reactor Coolant System should be throuah the CYC8 Mused Bed Domineralisers.
4.1.1 below 330'F. Isolate PERMS monitor RE 48000 prior to cooling dow t 4.1.2 i Degas the Reactor Coolant Systen to 15 co/km H prior to reactor shutdown pressurise or after resetor trip. The 2 i
shutdown. r vapor space may also be desassed prior to
, 4.2 H0DE 5 4.2.1 If the Rasetor Cooling System is to be opened for work NOTE Proper cleanup requires the Reactor Coolant System remaining -
Lressurisedandatleastone actor Coolant Pump operating.
L a.
Degas RCS tot 3 c 9/kg 5g and 40.05 uct/sm Re.133. "
{ -b. Reduce RCS Gross amma Activity to 40.1 uC1/ga.
L 4.2.2 If the outage is to he more than 4 days t o Generators should be placed in wet layup.he 8 team Clearance
- should not be hung on the following systems until the Steam Generator's wet layup parameters are within specification.
0 8
' if,'?F "
L g!,*=~rno,Q?
.... . ... m g y. we, 6 M [ t$f $'>$($
2.,. J VROP 49006 0
' 3, g' .7, g
,~ 0 '
9m '
.s 6 of 36 3
.a
- a. Condensate Storage Tanks.
'D
- b. Auxiliary Feedwater System. '
- c. Feedvater Layup Fump. .'
- d. Deatneralised Water Storage Tank,
- e. Water Treatment Plant.
- f. Stesa Generator geoirculation Pump.
3 Stesa Generator Blowdown System.
- h. Condensate System (Blowdown System cooling).
- 1. 8teaa Generator Layup Pump.
4.2.3 If the outage is to be more than 10 days the condensate and Feedwater system should be placed in wet layup.
The condenwate system should be long path recirculation with one condensate pump running condenser vacuva maintainedandtheAuxiliaryBoilerinservice. ,
Clearance should not be hung on the following system until the Righ Pressure Feedwater Mesters r.re 200'F and the Condensate and Feedwater System's wet layup parameters are in specification
- a. Condensate system
- b. Feedwater Heaters
- c. Feedwater System
- d. Auxiliary loiler
- s. Condensate 8torass Tank
- f. Deatneralised Water Storage Tank 3 Water' Treatment Plant h.- Feedwater layup pump 1
. . . . . -=_-- x
,. w w - n:. g r .:q q r tag pil g R % f f f M F W $ ' @ % I l h ,
, m:5ovna wo" .
naveson .s - ..e 7i pwm .
]
[
VEGP-49006.C 0 7 of 36 '
}4[
5.0 TYPE IV.. EXTENDED y0RCED OUTACE ST NODES
.i 4.,
5.1 MODE 8 3 or 4
"i p,
When the Reactor Coolant System .S ' t orature is decreased below b" 350 F the solubility of activa,ted corrosion products i - (CRUD in a )' Crud Burst".. The increases which results - Purification flow rate should be maximised and any draining from the Reactor Coolant System should . be throuah the CVC8 Mixed Bed Domineralizers. ; 5.1.1 Isolate PERMS sonitor RR 48000 prior to cooling down below 350'F. 5.1' 2 . Degas che Reactor Coolant Systeer to 15 cc/kg H to reactor shutdown or after reactor trip 2 P'i ' 3.2 MODE 3- - 3.2.1 If the Reactor Cooling System is to be opened for work NOTE Proper cleanup to tres the Reactor Coolant 8 tes remaining brassurisedanda least'one actor-Coolant: Pump operating. -
- a. Degas RC4 to45 cc/kg 52 and 40.05 uct/gs Xe-133.
b .. Reduce RCS Gross Gamma Activity to (0.1 uC1/Sm. ' 5.2.2 If the outage is--to be more than 4 days.the Steen
' Generators should be-placed-in wet.layup. Clearance should not be hung on the following-systems until the Steam Generator's wet layup parameters are within specification.
i i 6
^
r g-
__ __ _ _- ._ m - - - - .. . _ _ . - ..; - .
, gg -~
.........r.
.y!. A = ~ 4 -
-m>was30 ~) 355% biYdj$
,.o, g ,
, . 3gm.,n , ,. g., . garN5----
.<- i VEGP 49006 c'. ' ~- ' ' ' "
'O OT'-E ~ -
8 of 36 '" b 6 i, a. n Condensate 8torage Tanks. g;3l1 W. c b. Auxiliary Feedwater Systaa. .
..yl
'l c.
yeedvater Layup Pump. '
*d. Domineralised Water Storage Tank. ' ['fh ;
- e. Water Treatment Plant. (
- f. 8 team Generator Recira.ulation Pump.
- g. Steam Generator Blowdown System.
- h. Condensate System (810wdown System Cooling),
- i. 8 team Generator Layup Pu g .
5.2.3 If the outa8e is-to be more that. 10 days the condensata and Feedwater systes should be placed in wet layup. The condensate systes should be long path recirculation ' with one condensate pump running, sondenser vacuum maintained and the Auxili . Boiler in service. Clearance should not be on the following systes 'n until the Righ Pressure Fe stor Heatera are 200'F and the Condensate and Feedwater System'a wet layup parameters-are in specifications
- a. Condensate-system
- b. Feedwater Heaters
- c. Feedvater Systes
, :d. Auxiliary Boiler
- e. Condensate Storage Tank -
. . , .. .x.
- f. Desineralised Vater Storage Tank ..
8 Water Trestment Plant
- h. Feedwater layup pump t
4 90344)
f P "- emociountna
' , mis on "' ., pga no, ;
VEGP 49006 C ' 0 - 9 of 36 I;t 5.2.4 } If the outage is to be longer than 60 days it will be necessary to place the High Pressure and Low Pressure .1 E* ,
[( .
Turbinesunderhumiditycontrolleddrylayupalunf guidelines in the Plant Extended Life Layup Manus . 5.3 f;~}j; HDDI 6
'86 5.3.1 *h If the Reactor Cavity is to be filled or the head is to ,3 be removed,
< 0.05 uCi/gm.than reduce the RCS Oross Gar:ma Activity to "7
'23 NOTE If 2565 is one of the o monitors in step 5.3.2,perable than either Channels 2565A and 2565B (considered one channel) or 25650 must be operable.
5.3.2 The 2 outinofMode operable 3 of the 6: following PERMS monitors shall be RE-0002 RE-0003 RE-2565 5.3.3 A complete set of analyses for all sample parameters listed in Section 3.6 of Control During Refuelina" procedure 35180-0, " Chemistry hours) shall be current (within 24 Vessel. prior to moving fuel elements in the Reactor i l mun
.--w--
-mm,xtmWh%% & W R$h$Y0N Pnoctovna NQ, ?
RgymoM
.. 'g ., , , . 3,p,., .
Mcg No, VEGP 49006-C
. . ,q 0 .' . y' -
. 10 of 3'6' E '
= ,
6.0 ' 4 TYPE V - SCHEDITLED OUTAGES BY NODES AND RETUE 6.1 HODES 3 or 4 l NOTE r. When the Reactor Coolant System d. temEeratureisdecreasedbelow 350 F the solubility of activa,ted corrosion products *N de; (CRUD) increases which results in a " Crud Burst". The ".".4
~
Purification flow rate should be maximised and any draining from l the Reactor Coolant System should be through the ' l Domineralisers.CVC8 N:Aed Bad .: 6.1.1 , below 350'F. Isolate PERMS monitor RE 48000 prior to cooling down , 6.1.2 . Degas the Reactor Coolant System to 15 cc/kg H prior to reactor shutdown or after reactor trip. 2 - j 6.2 H0DE 5 6.2.1 If the Reactor Cooling System is to be opened for work ' NOTE Proper cleanup requires the Reactor Coolant System remaining pressurised and at least one Reactor Coolant Pump operating, s. Degas RC8 tot 3 cc/kg H2 and (0.05 uC1/gm Xe-133.
- b. ,
Reduce 108 Cross Ganssa Activity to < 0.1 uci/gm. 6.2.2 If the outage is to be more than 4 days t Generators should be placed in wet layup.he Steam Clearance should not be hung on the following systems until the - Steam Generator's wat layup parametare are within specification. - swi
~: -
. . . .. .... . 9,q - q q tr y inoctovuMS
.gy,gggp r. . .j , p.
ey...:.U
, g y; newow paos a -
VECP 49006 0 0 11 of 36 '
- s. Condensate Storage Tanks.. ? .-
i
- b. Am iliary Teodwater System. .
.y I' <
- c. :!4 4%
Feedwater Layup Pump. i
.. %3$ ;
- d. Domineralized Water Storage Tank. 4
- g,5 .
- e. . Water Treatment Plant. - '
f.
.: . d#
Steam Generator Recirculation Pump. Q,
- g. Steam Generator Blowdown System.
Y
- h. ..
Condensate System (Blowdown System Cooling). 1". .
- 1. Steam Generator Layup Pump.
6.2.3 g If the outage is to be more than 10 days the condensate O and Feedwater system should be placed in wat layup. The condensate system should be long path recirculation .b l with one condensate pump runnina condenser vacuum - fis maintainedandtheAuxiliaryBoIIerinservice. di-Clearances should not be hung on the following system 5d-until the High Pressure Feedwatar Heaters are 200'F ' chemical parameters are in specificationsand the Condens ,c.
;f,
- a. Condensate system ',
'l q
- b. Feedwater Heaters c.
Feedwater System :
\
- d. .s; Auxilf.sry Boiler
- a. Condensate Storage Tank
- f. Domineralised Water Storage Tank g ,
- g. .)
Water Treatment Plant
- h. Fendwater layup pump " i I
}
.s 4
a
-4 '
9 , te
.c -
03ans l
-n--
J - ~ -* = l
- p. .; s ..v 6.2.4 If the outage is to be longer'than 60 days ic vil, be {t'T
) necessary to place the High Pressure and Low Pressure ';! Turbines under humidity controlled dry layup along ,. s I guidelines in the Plant Extended Life Layup Hanual. ' 6.3 HODE 6 ' ' 6.3.1
)
be removedIf the Reactor Cavity is to be filled'or the head is to
<0.05uC1/gmpriortoopeningreactorvesselhead.then re NOTE If 2565 is one of the o monitors in step 6.3.2,perable then either Channels 2565A and 25658 (considered one channel) or 23650 must be operable.
6.3.2 The 2 outinofMode operable 3 of the 6: following PERMS monitors shall be RE-0002 RE-0003 AE 2565 , 6.3.3 A completa set of analyses for all sample parameters listed in Section 3.6 of Control During Refueling" procedure 35180-C, " Chemistry hours) shall be current (within 24 Vessel. prior to moving fuel elements in the Reactor 6.4 Refueling 6.4.1 Rk'ST Cleanup
- a. i The RWST is normally recirculated through tha Sludge Mixing Pump and Heater.
i-NOTE 1 Step 6.4.1.b is for water clarity purposes. N
. _ ~ -
.~
m,~%-m.6ITITA65MT. f _me_. .._ .-- f 1. ', VIGP
._ . m ...,. .. .. ..3 ..
49006-C' "O - 13 of 38 '.
.9
- b. ..
At least four weeks prior- to be8 1r.nina of c.uta8e, recirculate RW87 with the 8 pent Fuel Fool i-
- q Purification Pump until the sDomineralisers and Filte 1
" suspended solids is obtained.pecification for
.0
.p.
N SPEC: SU8 FENDED 80 LID 8( 0.350 FFM 6.4.2 8 pent Fuel Fool
. ;'j
' t
- a. %
The spent Fuel Foci is normally lined up to the ' i Spent Fuel Fool purification system. Just prior 6.4.1.b.to the outage the RW87 is lined up per 8ectlen I b. Berate Fuel Fool to refueling Concentration
* ( > 2000 ppm) one month prior to outage..
- c. ,
When the RWST has been cleaned up, insure SFP Purification S , recirculating.ystem is rea118nad to the BFP and < 6.4.3 Replacement of Letdown Rasin Bede i
- s. Nimed Red Resin The in service CYC8 Nimed led should haya a DF of i 3 50 for 1-131 and or C The standby CVC8 Mixed Bad should be new ando.38 unused.
- b. Cation Red Resta L
L Lithium removal.The CVCS Cation Bed- should
- c. .
Rosinbedsshallberegatedasnecessary. least one reslacement At tion Red-and Two ' replacement Maed Beda should be=available. - 6.4.4 , Reactor 0 3 Coolant Systen Cleanup with Hydrogen Feroxide (H22 .'
- a. Laboratory Preparation 9
i h _q o
. x ,,, .ss r-
'iif"enoche .
~' ~
sp 1 Pre are Hydrogen Peroxide (H 0 f$ , ; metgodforPhotospectrometer.2) 2 analytical . ig: i
.3 2.
Order Plastic cuvetts for spectrophotometer. $'
- 3. Prepare Nickel 4 ,
Atcate Absorptio(n Photospectrometer.NL) analytical - S
- 4. cl Develop Calibration curves and standards
. ,!v.
necessary to support analytical methods. 4 NOTE ' Cleanup may generate Gross Cassna U activity 1.0 uC1 /ge. levels in excess of The Purification - flowrate should be maximised and any drainage from the RCS should '- Se chrouah the CVC8 Mixed led Domineraliser. .
?" ;;;
- 3. Perform a Structured Briefin Technicians on Radiological eafety g for Laboratory in 'k:I handling Reactor Coolant Eamplea from cleanup. Technicians need attend only one structured briefing on this topic,
- b. At shutdown t- 1. Begin 4 hout Cause Isotopio analyses and -
l elemental analysis for Ni with the technical soscification analysis for DEQ 1 131 and obtain letdown flow rate. ,
- 2. Ensure Operations Department borataa RCS to refueling concentration. ?
f.. f Berate as necessary te keep up with the .!
$c.
removal by a new resin bed
- 3. Be Np:
angin-de8assingfrom15ccjksto43cc/kgH 4 0.03 uC1/gm Re 13 2 $-
.i 3..
'q,;.
iA
* .q
} .
.y 7..e ., y .. .
N m a , .. , 70M44
m _ __ .m.. m A= _mf '---. mea J.-_- d >* _..e r= 4+-- 4*A_a-.. _J. Ja
* ._. ._._-._e ..___._ ..- - -- '
c.---:.v. m e PROC (DURE NO. " R gyg{, . ;' ,9f.Q6&&%CW[6$.Th
. 9,, P W No.
lb5 <.' VEGP 49006-C * ' "
,,3 A
=
0 m ;t. /" ' 15 of 36 -
, ,. '} -
4. 11 ace a new CVCP.
, . ..., Nixed Bad in service. ,e
'a,,
Draw Gamma !sotopic and B , DF samples eyety 4 hours,oron T b, ; When Boron DF ise <'10 analysie may 3 [i be stopped, Continue Gam,ma Isotopic 1,' f analyses until cleanup is complete, q a,
- c. Cooldown/Draindown gg NOTE "3 ,
Draining of the RCS shall be through the purificatica (CVCS) Mixed Bad domineralizer at approximately 75 gallons per . minute. Flow de system pressure. pends on .
- 1. .,
The plant should have been placed on RHR, Nj cooled down to 110'F and drained down to ' midloopviathepuriItcation(CVCS)mixedbed I domineralisers prior.to H 02 2 addition.
- d. Cleanup o 1.
i When the draindown is complete Hydrogen l Peroxide should be added. k-NOTE This cleanup will require a l minimum of 60 pints of 4 uninhibited hydrogen peroxide ,;
' (H220 I'( : 9 s,
- . l
- 2. Add 10 pints of uninhibited H 0 f 22 Maintain a.0.5 ppa 0,,
concentration and 0.5 gpa H o residual, with a maximum of 10 ppm yHgg2 2 addition.
't i
t c. I Sit - www _
.,_e ___.__ _ _ _
enoctoun so. , , , . .. . . m 7.tg.$gy
.. 4 2 W.) ?
n;. ... ,..
~khX[,%@,fd)hyh.
VEGP
.,u g.g pde no, 3 490d6-05 ..m 'jc y g[ i E:SQ. hgf[,,
'gg; .' iy -
#:l, '
, 16 of 36- 'l.hh{!
.'}:!CN?tOilNW4,$&$.Q(%,.p%<
n
~
3eN Place-stan .
\
, ..D! necessary. . ; dby
* ":i:V. idze s bed in service as 9
,y .,.
l Replace used Mixed Bed-as Necessary. 4 '9 Co-58 activity w vaing RHR pumps.ill peak. . Continue cleanup 4; NOU a ; e ! Dose Equivalent Iodine should i be below 0 luci/gm and Xe-133 below 0.05 uci/gm prior to 1 opening the Reactor Coolant System. 5. Continue cleani.p whila on RRR through the purification less than 0.03 system uct/ga.until Co-58 activity is
- 6. ' A new purification placed in service pr(CVCS) mixed bed should be being filled. ior to the Reactor Cavity 6.4.5 normally be operational prior; to H0DE-6 PERMS RE-2532A RE-2532B RE-2533A 4 4
RE-2533B . 4 RE-12116 RE-11117 RE-2565A RE-25655
..r RE-25650 . .
' 4.,g" ,
RE-002
, esY RE-003 *!I.
- . W 3
~
w-
=
_ _ - .cw w : m_m
. . & s 4 3~ twi*? ' ((,hk
- 0" { Pnoctavat No,
- t '
.e. ngymon . ; ,g . . , , gag so, i
{. t VEGP 49006-C'. " N .2 0- '
'17 of 36 c \
, .., l. g 7.0 f
.[ PLANT SHUTDOWN /C00LDCNtr Urgent or Emergency Cont.ainment Entries are performed
" Containment Entry".in accordance with Section 4.2 of Procedur 7.1 MODES 1 TO 3 7.1.1 Radiological Precautions 7.1.1.1 Containment Entries durina modes 1. 2 performedinaccordancewIthSectiond.3,or4are 00303-0, ',' Containment Entries". 1 of Procedure 7.1.2 Reactor Coolant System 7.1.2.1 If there is greater than a 151/Br reduction in reactor shutdown.power, or the reactor is scarced up or thermal Data Sheet 5 of 35110-C " Chemistry Control Of The Reactor Coolant Systca", mus.t be completed.
Operations Department will be borating the reactor
' coolant system to shutdown concentrations and requesting analyses.
7.1.3 Steam Generators 7.1.3.1 At less than 31 Reactor power transfarredtotheAuxiliaryEsedvaterPumpa(AFW the Steam Generators are Steam Generator Blowdown continues in operation. ). 7.1.3.2 If chemicals has been tricted are not added'to the CST or the reactor feed u it may be necessary to align chemical pump. p to AN pu,mp discharge using the Feedwater Layup y , 7.1.3.3 Chemical additions to 8 team Generators are made in accordance with Section 3.9 _ Condensate _ chemical Injection When operation or Procedure the Plant is__in Heatup or Low Power 35535-0 " operation of The concensate.ChemicalInjectionIystem". 7.1.3.4 The Steam Generators are sampled once per shift in accordances with Section 4.7.1 Heatup/Het Standby JGreater than 220'F Less Than or Equal to M Power of Procedure 33210-0 " Chemistry Concrol Of The Steam Generators". e t
,, 3 . #
se
.,y , ,- *
' 70$448 - , ,, . .f h'
" , w l * * ? W e= i * " * *
- w ,e
_ _ . _ _ . _ . _ _ _ _ - - . - - - - - - -~~
~
__ = r ,_ s -
)
weMS)T . %@$>.,%!@$ff sed'"h>
. enocnounn uo,
- ~
m us VEGF 49006-0 ' w.i. .k.h.. .h.*h,' ,
~18 of. 36 '
#c:
1' 7.1.4 Secondary System t i, .- 7.1.4.1
}
Prior toches!a reaching 251 power and chemistry or after trip,Hyd.* a can make cal additions of Awoontum r a ne ~ to the Condensate Storage Tank (C8T) in accordance with ' Section 4.8 of Procedure 35250.C, " Chemistry Control of , The Condensate Storage Tank". . 7.1.4.2
'. t ,
. The Heater Drain pumps should be stopped when the Reactor power is below 25! Power. 7.1.4.3 One Main Feed Pump (MFP) is secured below 31 power. 7.1.4.4 CEemistry should request that the~ Condensate and
- Feedwater If the outage systems is to be remain in long path recirculation.
10 days, Bectinn _4.6 Shutdown - Short Tara wat Larus, of Procedure 35220-c applies. control or The consensate And Feedwater Sys,taas","cneststr 7.1.4.5 If the outage is to be 10 days l
- . preparations for wet lavun of co Chemistry should
- ake ndensate and feedwater systems in accordance 35220-c. The system should be operated dth Section 4.5.2.2 of Procedure with f,ne L condensate Hesters ar pump until th3 High Pressure Feedwater condenser.e 200'F and vacuus 10 broken in the 7.1.4.6 Chemiar.ry B o artment should confira no tube leals in aal watarocaes of the Circulating Water System via Amartap System,-prior to securing condenser vacuum.the 7.1.5- Support Systems l
7.1.5.1 l The Auxiliary Boiler-is started below 251 Reactor and the !$( plant should-be placed in operation. The-Auxiliary feedwater.3 oiler will require about 150 spa of makeup < , 7.2 MODE-3 C00LD0VH 7.2.1 Reactor Coolant Syrtes 4 F _ - . + . _.. . . _ .
- _ 33 i g.s . ftT,5$ $'$. $
\ f' "**"* :
. :. M93
?-
' syn :9? W . '
*** t *- .
".0 ; 19 of 36 y-f 7.2.1
.cansfer Hydrogen.VCT to Nitrogen and Degas to4 15 cc/kg i then it should be daIf the RCS is to be opened for maintenance -
0,05 uCi/gm Xe 133. gassed down to (5 cc/kg N ' and 7.2.1.2 Reactor Coolant System chemical parameters must be ~ wfthin specifications of Table 1 of Procedure 35110-c.
" Chemistry Control of The Reactor Coolant System".
7.2.2 Borated Water Sources 7.2.2.1 When RCS Pressure is below 1000 pais no lonaer require Technical specifica, tion the accumulators surveillances. 7.2.3 Stoca Generators 7.2.3.1 Sample once per shift in accordance with Section 4.7 of Procedure 35210-C, " Chemistry control of The steam Generators". When steam generator pressure becomes too low dump,s to Atmospheric relicfs. Operations Department will transfer from 7.2.4 Secondary will be secured,When steam pressure becomes too low, the main feed pu i 7.3 HODE 4
-7.3.1 RCS/ Reactor Heat Removal System (RRR) -
HOTE When the Reactor Coolant System t erature is decreased below 350 F to 140'Fco the solubility of activated rrosion products (CRUD inc decrea)ses,reases which as temperature results in a
" Crud Burst". The Purification flow rate should be maximised and any draining from the Reactor
- Coolant system should be through the CVCS Mimad Bed Lenineraliaers.
_ , ;g PROCEDURE No
~
'mgyggaON VEGP PAQt vo.
49006-C 0 f 20 of 36 7.3.1.1 At 340*F / 425 poig at 1saat one train of RHR can be put in service. of RKR. Chemistry must perform Boror analysis of Table I and Table 2 of Procedure 35110-C.RHR parame 7.3.1.2 If a HODE 6 entry is anticipated, commence ! prerequisites for HODE 6 entry, Section 4.6.3 of this procedureOutage. Refueling for Extended Outage a td Section 4.6.4 for a 7.3.2 Borated Water Sources 7.3.2.1 The Refueling 9ater Storage Tanks and Boric Acid Storage Tanks should be sampled for Boron. The specifications 30090-c are stated in Section 5.1 pf Procedure Coordination"." Chemistry Technical Surveillance Performance ! 7.3.3 Steam Generators 7.3.3.1 below (N ) t 25 psig, request operations initiate Nitrogen 2 Steam Generator of 2 to 5 psig. 7.3.3.2 If the Steam Cenerators are to be in wet layup for more than 4 days. :oordinate with operations department in adding chemicals and increasing water levels to 50
-1001 Narrow Range indication in accordance with Section 4.6.3 of Procedure 35210-C. " Chemistry control of The Steam Generators".
7.3.3.3 If the Scena Generator parameters do not meet the specifications stated in Section 4.6-of Procedure 35210-C then a series of fill and draining evolutions coordinated with Operations Department may be required. 7.3.3.4 Wet layup should be postponed until HODE 5, 140*F. When cooldown rate would not be affected. Clearances should not be0,. steam hung on the AuxL11ary Feedwater system urt11 the orators are at la paranete.s ars within spee:rup levels are all chemical nfication. 7.3.3.5 Each drs.ining and refilling evo.'.ution takes approximately 8 hours per Steam Generator. l i
-u ----
--~%----- ,mm iqi
' PROCEDURE No.
REYlSJoM ~ VEGP PAGE NO. 49006-C 0 2 of 36 7.4 HODE 5 7.4.1 Raciological Precautions 7.4.1.1 Outage Entries during modes 5 and t are performed in "Ccnttinment Entries".accardance with Section 4.3 of Procedure 7.4.2 RRR 7.4.2.1 Prior to entering the RCS to > MODE 6 Operations should be borating cc/kg should be completed.2000 ppm and RCS degas to less than 7.4.2.2 The RCS/RHR Crud Burst should be in progress and sample should be drawn every 4 hours on RHP, the outlets of ti.e CVCS heat axchanger, and the CVCS Mixed Bad Domineraliser. cleanup rate determined.Co-58 activity should be plotted and 7.4.2.3 Purification flowrate should be set at 120 gpm. The RCS should remain pressurized with at least one main coolant pump running until the prerequisire specification for the outa 4.6.2.1 of this procedure.ge is reached, see Section 7.4.3 Steam Generators 7.4.3.1 At 140*F, if the Steam Generator chemical parameters do not meet specifications of Section 4.6 of Procedure 35210-C then a series of dra evolutions will be necessary.ining and refilling Chemistry shall calculate the number of draining and refillings needed co bring the Steam Generator chemical parameters within specification, see Section 4.11 Useful Formulas of , Procedure 35210-C. 7.4.3.2 When Steam Generator parameters are in s accification, chemicals may be added fo* 1a generator recirculation pump yup using the steamno Steam Generato should of 4.6.4.4 beProcedu recirculated in accordance with Section made as necessary re 35210-C, and chemical adjustments 7.4.4 Secondary w..
.- p .y. m , .n- w . -
,i inoctount w m VEGP '49006-C am --
l.; l 0 22 of 36 ' 7.4.4.1 If chemicals have not been added to the feedvater and condensate-system, they should be in accordance with Section 4.5.2.2 for long term wat layup or Soction
" Chemical Control Of The Condensate And Feedwat System".
7.4.4.2 ' The feedwater henters should be layed up in accordance with Section 4.5.2.3 and a g led in accordance with Section 4.5.2.4 and Section 4.5.2.5 of Procedure 35520-C. 7.4.4.3 When layup of feedwater heaters is completed then the Condensate and yeedvater system should be placed in short path recirculatiet.. 7.4.4.4 Outdelines for the layup and inspection of Feedwater Heaters and Main Steam Reheatere during extended outages and periods when internals are open to the Atmosphere are found in the Plant Extended Life and Plant Layup Manual. 7.4.5 Perms Monitors 7.4.5.1 Reset RX-0002 and RE-0003 to the low set point of 10 mrea/hr. 7.4.6 Turbine Plant Cooling System i The Turbine Plant Cooling Tower, Circulating Water be secured during. refueling outages. Cu system delinesand for Turbine Pla the layup and inelection of these Plant sponents are described in the ?lant Extended Life and Layup Manual. 7.4.7 Nuclear-Service Cooling Water The Nuclear Service-Cooling Water System Cooling Towers and systen heat exchangers shode be isolated and inspected one train at a tir. Widelin'= for the layup and inspection- of theso ::, ant camps nts are described Manual. in the flant Extenf;d Life and L. yup 7.4.8 Radiological Precautions nua l_____-___ _-_ -- - . . , .
emoctovat No. _. '.?
~
ngyision nog no. VEGP 1, 49006-C 0 23 of 36 - NOTE Containment cannot be ocr. spied when the In-core Detectors are c,perated or less t. hat '911y inserted. 7.4.8.1 Prior to opening the containment for outs a work OperationsDepartmentshallcompleteSectfons3.d.1and 3.2.2 of Procedure 00303-r Containment Entries and a clearance shall be hung on,the breaker for the In-core Detector Drive notors so they can not be operated. 7.4.8.2 Prior e.o outags opening the containment for outage work, entries Health Physics will establish radiological sample and survey data an,d air quality status utilizing air pada per'RP procenures,in accordance with Section 4.3 radiation of Procedure 00303 C, " Containment Entries". 7.5 MODE 6 (REFUELING) 7.5.1 A complete set of analyses for all samles and p' Chemistry Control During Refueling"rrameters shall be currentlisted in Sectio within 24 hours prior to moving fuel, elements in the reactor vessel. 7.5.2 Refueling Pathway 7.5.2.1 When the Raactor Cavity is flooded, prior to and during fuel transfer, obtain daily Boron samples of RHR Troin in service Reactor Cavity Refuelin5 Canal Transfer Canal Spent Fuel Fool 7.5.2.2 When flooded, the obtarefueling canal in the containment building is per 24 hours a tritium analyses on ':he Plant Vent once 7.5.2.2 During a first: refuelin when apunt fuel is in the spent fuel pool,gtritium of a unit, aanlyses on plant vent once ptr 7 days it required. I
,e w . -
m oc w ai ,,o. - . .v.cmeg.r W.WM? '< ' 1 Pfg i
.,s, ,,
VEGP 49006-C
'. . 1. .n 0 24 of 36 'hi ,
7.5.2.4 If both of the minimum of 2 required source ringe neutron flux monitors inoperable, determine the boron i concentration of the reactor coolant system once per 12 hours controlper Section During Refueling". 3.4 of Procedure 35180-C, " Chemistry 7.5.2.5 Place the the standby cavity for refueling. mixed oed in service prior to filling 7.5.2.6 , l Purification of the coolant via the RRR loop and low pressure purification loop must be maintained continuously while the reactor cavity is flooded. 7.5.2.7 The reactor cavity should also be filtered and domineralised continuously durius refueling operation and again after recurre to the RW8T. ; 7.5.3 Radiological Precautions NOTE Contairueent cannot be occupied when the In-core detectors are
- operated or less thar fully inserted.
Prior to flooding the reactor eavity locked or posted access shall be established on the co,ncrete pluga for the fuel transfer tube ballows in the Puel, Randling Building and Containment auilding. 8.0 Z!F MATUP/8TAltTUP 8.1 PRRREQUISITES l 8.1.1 DM plant Boiler should be is started up.plued in service when the Auxiliary ( HOTE ' l l During the secondary recovery from system outaae,be should aleaned up for several days prier to plant startup. 1 I 8.1.2 The secondary plant should be in tons path racirculation l l M
*=. . _ ,, _ -
_~.-2 muasammaassiniiiniliWAmia
, ..w v.*
- 746ctovatNa namion VEGP 49006 C Pha a 0
25 of 't, 8.1.2.1 N Auxiliary Boiler is in operation. 8.1.2.2 . A condensate polishers are'in cump should be running and the condensate operation. 8.1.2.3 Vacuum is drawn on the main condensers NOTg If the On-line analysers are not available, then grab samples must be obtained, per section 4.11.1 of Procedure 35220-c. 8.1.2.4 The following secondary on line analysers should be availables
- a. Condenser System 1.
Condenser Hotwells (6) - Cation Conductivity
- 2. Condens,ar Pump Discharge Cation Conductivity Specific C nductivity Dissolved Oxygen Silica Sodium
- b. Feedwater System 1.
Feedwater Chemical control sample point Hydrasine ! 8pecific Conductivity 2.
' Feedwater Pump (A&B) inlet - Dissolved oxygen 3.
l Feedwater Pump (Ar8) Discharge - Dissolved 0xygen t 6 l (
_ .. .. . ..... . - - - e - - -
., .... ..m..,,
NME No-
.y navmon Paoa wo, s
VECP 49006-0 0 '4
- n. 26 of 36 l-l2, 4
- n Feedwater to 8teeJe Generator Specific conductivity Cation Conductivity !
H drasine .. Turbidity Sodium *- Dissolved Oxygen - 8.1.2.5 When the condenser vacuurs te drawn, no condenser tube the Aasrtap syste:toleakage should be verified by helium leak the circulating waterboxes. > 8.1.3 PERHS Monitor 8.1.3.1 The following PERMS monitors should be available (All HODES). RE-0018 i RE-0021 RE-0020A RI-00208 RE-0848 M-17644 RI-12116 M-12117 RE 12441A or RI 12444A RX-12442B or M-124448 RE-12442C or M 124440 FT-12442 or FT-12444 FI-12442 or FI 12444 l t When a release is in progress via this pathways RE-12839A RE-128393 RE-128390 FT-12839 8.1.3.2 The following monitors should be available (HODES 1-4). RE4003 RE-006
._. _. __ _.- - __ . _ _m . __ ._ . _ _ _ _ . . _ _ _ _
y ~ ~ ~_st"*~*~**t=**'-i -
* ; * ?, * ** * '
PROC 400AtNV.~ RsYlWoM PAQt NO, VEGP 49006-C 0
'y{
27 of 36 M' ' i 8.1.3.3 The following PERMS Monitors Hust be available (HODES 1-4) to change modes during startup. RE-002* RE-003 RE-2565, (A and B) or C RE-2562A RE-2562C
*(A2and outB)of 3 of these monitors taust be .available or 25650 must be operable for 2565 to be 2565 considered operable.
8.1.3.4 The 1-3) following to ChangePerms modes.Monitors must be available (HODE RE-13119 RE-13120 RE-13121 RE-13121 8.2 MODE 6 TO H0DE 5 8.2.1 Reactor Coolant System 8.2.1.1 Reactor Coolant System chemical parameters must be
.within specification of Table 1 of Procedure 35110-C,
" Chemistry Control Of The Reactor Coolant System".
8.2.2 Borated Water Sources 8.2.2.1 When the water from the reactor cavity is pumped to the RWST, the activity in the RWST must be reduced, recommend to Operations Department that the RWST should be lined up to the spent fuel pool purification system. d.2.2.2 The refueling water storage tank and the boric acid storage tanks should be sampled for Boron. The specificattor.; 30090-C are stated in Section 5.1 of Procedure 1 Coordina, tion"." Chemistry Technical Surveillance Performance ! 8.2.3 Radiological Controls l 8.2.3.1 Decontamination of Ranctor Cavity l i
. :. __.---_=--m--- ,
qk.; . pqqg; .-w ~ ~ w, _- ' Ag h ,p 48 f7006-C
- n. e+ - 0 28 of 36 l 8.2.3.2 When the Reactor Cavity has been drained, the locked and posted access on too concrete plugs for the Fuel l Transfer Containmenttubeshould bellows in the Fuel Handling Building and be released, 8.3 H0DE 5 TO H0DE 4 i 8.3.1 RCS/RKR 8.3.1.1 Operations may begin diluting boron to operating concentrations.
8.3.1.2 ?te Reactorwith Coolant System should be lithiated in compliance control program.the coordinated lithium and boron NOTE While erforming oxygen scavenging using ydrazies additions, the CVCS 1 edown domineralizers should be bypassed and letdown flow diverted to the VCT. 8.3.1.3 Prior to exceeding 180*F: Oxygen should be below 100 ppb or sufficient hydrazine added to scavenge the oxygen, per Table 1 of Procedure 35110-C. Litium should be within limits of the Coordinated Lithium-Boron Control program per Table 1 of Procedure 35110-C. 8.3.1.4 PZR boron should not be different from RCS by more than 50 ppm. 8.3.2 Steam Generators 8.3.2.1 Steam Generator blowdown should be established. The following Steam Generator Blowdown monitors should be i available: Specific Conductivity ! Cation Conductivity ' pH Sodium . 1
. - :- .x enestnma wo.
~
esion
~~
;y eAna wo.
VEGP 49006-C 0 d 29 of 36 If the on-linn samples shouldmonitors be obtained. are not available, then grab 8.3.2.2
- If itthe to is desired environsto route the Steam Generator blowdown refer to Procedurs 36001-C " NPDES ImlesentationkndControl"fornon-radiological of luent requiremsnts and Procedure 36010-0 "Offsite Dose Calculations Manual Control"forradiological(ODOf)ImplementatIonAnd effluent requirements.
B.3.2.3 dteam Cenerators should be drained to operating levels.
" Chemistry Control Of Steam Generator Chemistry".In acco NOTE If Steam Generators do not meet specifications for commencing heatup of Section 4.7.1, then .
drain and refill to attain those specification that will be required. 8.3.2.4 Prior to exceeding 200'F on heatup the chemical p'arameters Chemistry of Control section 4.7.1 of Steam of Procedure 35210-C Generators" should be, within specification. 7f parameters exceed specification request operations hold temperature and performspecification. within correc,tive action to return the parameter en If parameters are within snacification notify operations that steam generator chemistry is satisfactory for operations above 200*F. 8.3.2.4 Steam Generator samples should be obtained once per shift while in Heatup/ Hot Standby. 8.3.3 Secondary 8.3.3.1 Steam Generator Blowdown Processing System NOTE The Steam Generator Blowdown . Domineralizers can be bypassed ., during startups and shutdowns. nous
wa_ moctovna no.
....., .... m p e -
r ,. VECP namo( ~'T. .. nog ,,o, ' Y 49006-C ~L , i " 30 of 36 a. The Steam Cenerator Blowdown Damineralizer Chemical parameters are stated in section 3.5 of Procedure 35225-C Cenerato: Blowdown "Processing Chemical Control Of The Steam System". b. Steam Cenerator Blowdown Processing system has an On-line analyzer at the outlet of each mixed bed Domineralizer tnd should be available. The following parameters are continuously analyzed.
- 1. Cation Conductivity
- 2. Specific Conductivity If the monitors are not available then grab saw les should be obtained in accordance w,ith Section 3.6.3 and 3.6.4 of Procedure 35225-C.
8.3.3.2 Secondary system cleanup is conducted in accordance with Seccion 4.7.3, Secondary / Cleanup of the secondary _ system of Procedure 35220-c, " chemistry control or ne ' Conderiaate And Feedwater Systems", a. The secondary plant should be operating in long path recire with one condensate pump running, with a condenser vacuum until Fe (100 ppb and 0 < 100 ppb. 2 b. with ecodex filter mediumThe condensate polishers are placed in ag when Iron (Fe ) is within specification the e, codex is replaced with the Hydrogen form resin Chemistry control of the condensate polishers are. maintained in accordance with Section 4.6 Operatinst Chemistry control of Procedure 35320-c " chemical contro; or no CondensatePolish[ngSystem".Whenoperatingthe condensate polisher the following On-line analysers should be,available: NOTg if On-line analyser is not available, then grab samples should be analyzed per Section
- 4.7.3 and 4.7.4 of Procedure 35230-C.
I
enocaovatwo. : ~'y, namon VEGP 'eAos no 7 49006 C 0 31 of 36 1. Individual Polisher Bed Effluents i
- a. Cation Conductivity
- b. Sodium
- 2. Combined Polisher Effluents 1
- a. Cation Conductivity .
- b. Specific Conductivity
- c. pH
- d. Turbidity
- e. Sodium
- f. Silica 8.3.3.4 The feed and condensate system chemical parameter for greater than 200*r to 51 power are listed in Section 4.7.2 of Procedure 35220-c. At 200'F are analysed on the Condensate and Fee Chemical dwater system, Samples
' operations is notified that the Chemical parameters are satisfactory for operation above 200'F. ,
8.3.4 Radiological Precautions NOTE Containment cannot be occupied when the In-core Detectors are operated or less than fully inserted. ! 8.3.4.1 i Prior on to Mode 4,for the the breakers In-core Detectormotors driveoporation so they cannot be operated, t 8.3.3 PERMS 8.3.5.1 The 250'F.following monitors should be available prior to ' RE-12839A RE 12839B RE-128390 , FT-12839 f h 4 m* c.
, . L- ,+1.ws.n~ M L"'-
. - w .. .
4 ' PMoctDW u No. mayassou proTWo- 'Y. .. VEGP 49006-C 1 @t 0 32 of 36 ., 8.4 H0DE 4 TO NODE 3 8.4.1 RCS/RHR . 8.4.1.1 Prior to exceeding 250'F, Chemistry shall setcale the RCS andppt than 100 PZR for dissolved oxygen, which must be less 8.4.1.2 When reachedPZR heacup begina and saturation temperature is ' service., place the PZR steam space sample line in 8.4.1.3 Between down. 300'r and 330*F RHR is isolated and cooled 8.4.2 Steam Generators 8.4.2.1 When the steam generator pressure reaches 25 pais, isolate the nitrogen to the steam generators. 8.4.2.2 The following Main Steam monitors should be available Cetion Conductivity pH Sodium Process Monitor If the on-line samples shouldmonitors are not available, then grab be obtained. 8.4.3 Secondary System 8.4.3.1 Place the CST in o dissolved oxygen. The peration, CST c hemical parameters shouldChemis be within specifications started in Section 4.5 of Storsge Tank". Procedure 35250 C. " Chemistry Control Of The Co 8.4.3.2 Above placed340'F the Auxiliary Faedwater pumps will be in autouatic. 8.4.3.3 Heatup rate will be maintained using the atmospheric steam reliefs or steam dumps. 8.4.4 Borated Water Sources ma
n - .~
. . .. . . . . ag enocep,at ho-nsym VEGP Put wo. O 49006 C 0 33 of 36 8.4.4.1 At 435'F and 925 psis in the RCS, operations will fill accumulators and gas pressure is adjusted after fill. ;
chemistry must sample for Boron, specifications are t i started in control of Section 3.3 of Procedure 35160 C. " Chemical the Accumulators". i 8.4.5 Radiological Controle 8.4.5.1 i 350'F.Re-establish flow throu8h RE-48000 prior to exceeding 8.4.6 PERH8 8.4.6.1 The 3: following monitors must be available prior to NODE RE-13119 RE 13120 RE 13121 REa13122 8.5 H0DE 3 TO HODE 2 Chemistry Department reports that the following system chemical parametere are within specification and satisfac;ory for power ascent Steam Generators Recctor Coolant System condensate and Feedwater System 8.5.1 Reactor Coolant System 8.5.1.1 Reactor Coolant System chemical parameters must be within specificatlons of Table 3 of Procedure 35110-C,
" Chemical Control Of The Reactor Coolant system".
8.5.1.2 Corrective serions should be taken if any parameters listed the in Table 4 of recommended Procedure 35110 0 are not within guidelines. be place on the volume control tank.Rydrogen Chemistrycover gas should superintendent shall make recommendations as necessary to obtain concentration within recommended guidelines. 8.5.2 . Steam Generators I 7034 5
~ .. -
PMoctWRt No. 'q' pgygfoM VECP 49006 0 PA04 4 0 34 of 36 , NOTE the over operation On8tartupIonsskouldbemet specificat i prior to exceeding 301 power, - this allows action level 1 values power. in Unit Startup to 301 8.5.2.1 Power operation chemical parameter specifications are listed in Section 4.8 of Procedure 35210 C. B 5.3 ' Secondary System 8.5.3.1 Chemical parameters for the secondary systems greaterthan51 power,arelistedinSectiond.8for Power , _ Ops . Condensate feedwater System or Procedure System and in Section 4.9,_ Power, F { 35220-0, "Chemicat j controt or condensate And Feedwater System". , 8.6 HODE 2 TO H0DE 1 i 8.6.1 Reactor Coolent System l l i ') l thermal powerIf there is greater than a 151/Hr redvetion in reactor .: Data sheet 5 o,f 35110-C, " Chemical Control Of Thethe rea Reactor Coolant System", must be completed. 8.6.2 Steen Censrators 8.6.2.1 The 35210-0 specifications of Sections 4.7.4 of Procedure The powe,r operating specifications 8sahould be met prior to e be met prior to exceeding 301 power. etion 4.8 should 8.6.2.2 Obtain and analyse Steam Canarator samples a minimum of with Procedure Section 4.7.4.2 35210 of ; C.once per shift while ramming up in po 8.6.3 Secondary 8.6.3.1 a MFP is started 8 team generators re At transferred 41 power, form Auxiliary Feedwater to M i one steam generator at a time. a n Fei.Jwater n... _~_
PROCsDURENO, AgYitioN
- k?
PAQL NQ, VECP 49006-C , 0 35 of 36 , 8.6.3.2 At 201 power, a Heater Drain Pump is started. plant power RAMP up to full power, heater drains areDuring directed back to the condenser, -
- a. Prior to Ope drain pumps, samples rations departmentto verif the starting the heater parameter of the system shoul be taken chemical and Steam Generator Chemistry monitored closely. Chemical parametersfromtheHeaterDrainSystemd.for greater than 51, are listed in Section 10
}8.eete? Drain Pum? Discharge - Power Operatio.ns, of Frocedure 35220=G, " Chemical Control Of Condensate And yeedvater System"
- b. Hester Drain system has no treatment to remove chemical contamination prior to introduction to l the Steam Generators and must he monitored. -
Heater Drain Pump Discharge Cation Conductivity 1 monitors are utilized for indication and must ! f either be available or grab sampled must be taken, i
- c. The following On-Line analyzers should be in service: ;
Heater drain pump discharge (A and B) Cation Conductivity , Sodit.m 0; 8.6.3.3 Above 301 power, at steady state power, and when steam ' generator chemistry parameters are within specifications the condensate polisher resin can be placed shift chemistry in the ammoniaforeman.form, at the discretion of the on i
9.0 REFERENCES
}
9.1 PROCEDURES 9.1.1 00303-1, " Containment Entries" , 9.1.2 01000-1, " Management Of Outages" 9.1.3 12000-1, " Refueling Recovery (MODE 6 To MODE 5;" l
.. , .s. , "~"
u zz_n__-__- - - - ------~ ~ ~ ^~
- . . n .. , n EktDLCE No, 7 MYlSloN VEGP PAQt No.
49006-C 0 36 of 36 [ 9.1.4 12001-1, "Unic 4)" '.feating To Hot Shutdown (HODE 5 To MODE 9.1.5 12002-1,
" Unit Heatup To Normal Operating" Temperature And Pressure (HODE 4 To H0DE 5) 9.1.6 12003-1,
" Reactor Startup (HODE 3 To HODE 2)"
9.1.7 12004-1, " Power Operation (HODE 1)" 9.1.8 12005-1, "Reacto? Shutdown To Hot Standby (HODE 2 To MODE 3)" 9.1.9 12006-1, '
"HODE Unit Cooldown 4)" To Cold Shutdown (HODE 3 To 9.1.10 12007-1,
" Refueling Entry (HODE 5 To MODE 6)"
9.1.11 30090-C,
" Chemistry Technical Surveillance Performance Coordination" 9.1.12 35110-0,
" Chemistry Control Of The Reactor Coolant" 9.1.13 35120-C,
" Chemistry Control of The Spent Fuel Pool" 9.1.14 35130-C,
" Storage Chemistry control of The Refueling Water Tank" -
9.1.15 35180-C,
" Chemistry Control During Refueling" 9.1.16 35210-C,
" Chemistry Control Of Steam Generatorn" 9.1.17 35220-C,
" Chemist;y Control Of The Condensate And Feedwater Systems" 9.1.18 35535-C,
" Operation of The Condensate Chemical Injection System" 9.1.19 01050-C, "IIsalth Outage Physics And Chemistry Department Activities" END OF PROCEDURE TEXT mu s
~
__ _ _ _ _ _ _ _ _ _ . _ _ _ - - - - - - - - - - - ~~}}