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
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HEA1.TH PHYSICS AND CHEMISTRY DEPARTMENT _ OUTAG
'I IMPLEMEhTING PROGADURE
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_ PURPOSE
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~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 defines the responsibilities for providing suppor,t.and 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, the duration and plant configuration.
depending upon If Svatem Outage, and g III = Short Forced e, _II ug - turn into g e - IV outages. this procedure will be applicaole.
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'
F 2.0 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 conducted by Chemistry for departmental personnel and w
representatives of all other responsible departments.
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2.3 CHEMISTRY OUTAGE PLAN Outline of Chemistry Deaartment 7.
2 Outage Activities develo Technical!Suppore Group.. ped and maintained by C2emistry
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2.4 CHZMISTRY RITENDED LIFE AND. PLANT LAY-UP HANUAL -
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4 Manual'for, Lay-upandinspISNi
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g-3.1 MANAGER-HEALTH PHYSICS / CHEMISTRY 7
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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.
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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 activities section of the Chemistry Outage Plan.'
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.
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3.4 CHEMISTRY. TECHNICAL SUPPORT' GROUP OUTAGE C
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3.4.1 Develop the Outage Chemistry Plan.
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3.4.2 about chemistry outage activities. Provide information T
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~n 3.4.3 Track Maintenance Work Orders written to perform Teclmical Support Group Engineers.inslections and cor ll,.):
u' 3.4.4 Attend.outage plannin 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
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in the Chemistry Operations Section during outagee.
ProvideothEnizationofIctivities.' technical 4
3.6.2 direction,And assignment of work tasks to implement
'I the Chemistry Program during outages.
3.6.3 Schedule qualified personnel in Chemistry Operations M.
Section to suppor. outage activities.
3.6.4 Review schedulerequestsforsupportduringoutages. schedule
.4 3.7 CHEMISTRY SUPERVISOR-SUPPORT a
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3.7.1 Provida technical expertise-and direction for personnel in the Chemistry Section Support group during outages.
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direction and assignment of work tasks to im the Chemis,try Support Program during outages.plement s'
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 including activities in the laboratory during outages.
3.8.2 Review che-totty data of all analyses performed by NuclearChemistryTechniciansdurangoutageslate conduct correlations for any abnormalities, and init 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 I
proceduras.
3.10.3 Review data for accuracy and identify and raport out-of limit r:onditions to Chemistry Foreman on shift.
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erature is decreased below activa,ted corrosion products lq%-
350 F the solubility of (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 Degas the Reactor Coolant Systen to 15 co/km H prior to i
reactor shutdown or after resetor trip.
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pressurise shutdown. r vapor space may also be desassed prior to i
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.
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Degas RCS tot 3 c 9/kg 5g and 40.05 uct/sm Re.133.
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Reduce RCS Gross amma Activity to 40.1 uC1/ga.
4.2.2 If the outage is to he more than 4 days t L
Generators should be placed in wet layup.he 8 team Clearance should not be hung on the following systems until the o
Steam Generator's wet layup parameters are within specification.
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Water Treatment Plant.
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Stesa Generator geoirculation Pump.
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Condensate System (Blowdown System cooling).
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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 System d.
Auxiliary loiler s.
Condensate 8torass Tank f.
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Water' Treatment Plant h.-
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5.0 TYPE IV.. EXTENDED y0RCED OUTACE ST NODES . i4., 5.1 MODE 8 3 or 4 "i -p, When the Reactor Coolant System .S ' t orature is decreased below 350 F the solubility of b" activa,ted corrosion products i (CRUD in a )' Crud Burst".. increases which results The 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. Degas RC4 to45 cc/kg 5 and 40.05 uct/gs Xe-133. a. 2 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-
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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 .1E*, [( Turbinesunderhumiditycontrolleddrylayupalunf f;~}j; guidelines in the Plant Extended Life Layup Manus. 5.3 HDDI 6 '86
- h 5.3.1 If the Reactor Cavity is to be filled or the head is to
,3 be removed, than reduce the RCS Oross Gar:ma Activity to < 0.05 uCi/gm. "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 out of 3 of the following PERMS monitors shall be operable in Mode 6: 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 shall be current (within 24 hours) 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 TYPE V - SCHEDITLED OUTAGES BY NODES AND RETUE 4 6.1 HODES 3 or 4 l NOTE r. When the Reactor Coolant System temEeratureisdecreasedbelow d. 350 F activa,ted corrosion products
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the solubility of (CRUD) increases which results de; in a " Crud Burst". The ".".4 Purification flow rate should be ~ maximised and any draining from the Reactor Coolant System should l be through the Domineralisers.CVC8 N:Aed Bad l 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, Degas RC8 tot 3 cc/kg H2 and (0.05 uC1/gm Xe-133. s. 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
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d# f. Steam Generator Recirculation Pump. Q, g. Steam Generator Blowdown System. Y h. Condensate System (Blowdown System Cooling). 1". 1. Steam Generator Layup Pump. ..,g 6.2.3 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 with one condensate pump runnina - fis condenser vacuum l 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.
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Condensate system 'l b. Feedwater Heaters q c. Feedwater System \\ .s; d. Auxilf.sry Boiler Condensate Storage Tank a. g f. Domineralised Water Storage Tank .) g. Water Treatment Plant h. Fendwater layup pump i I } .s 4 a 9, -4 te .c 03ans l
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{t' ..v 6.2.4 necessary to place the High Pressure and Low Pressure T ) Turbines under humidity controlled dry layup along guidelines in the Plant Extended Life Layup Hanual. s 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 out of 3 of the following PERMS monitors shall be operable in Mode 6: 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 shall be current (within 24 hours) Vessel. prior to moving fuel elements in the Reactor 6.4 Refueling 6.4.1 Rk'ST Cleanup The RWST is normally recirculated through tha a. i Sludge Mixing Pump and Heater. i-NOTE 1 Step 6.4.1.b is for water clarity purposes. N
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The spent Fuel Foci is normally lined up to the a. 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.. When the RWST has been cleaned up, insure SFP c. 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 3 50 for 1-131 and or C i Mixed Bad should be new o.38The standby CVC8 and unused. b. Cation Red Resta L L Lithium removal.The CVCS Cation Bed-should Rosinbedsshallberegatedasnecessary. c. At least one reslacement tion Red-and Two replacement Maed Beda should be=available. 6.4.4 Reactor Coolant Systen Cleanup with Hydrogen Feroxide (H 0 3 22 a. Laboratory Preparation 9 i h _q o . x,,, .ss r-
'iif"enoche ~' ~ sp Pre are Hydrogen Peroxide (H 0 f$, ; 1 metgodforPhotospectrometer.2) analytical ig: i 2 .3 2. Order Plastic cuvetts for spectrophotometer. Prepare Nickel 4 3. Atcate Absorptio(n Photospectrometer.NL) analytical S cl 4. Develop Calibration curves and standards necessary to support analytical methods. .,!v. 4 NOTE Cleanup may generate Gross Cassna activity /ge. levels in excess of 1.0 uC1 The Purification U 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 g for Laboratory 'k:I eafety in handling Reactor Coolant Eamplea from cleanup. Technicians need attend only one structured briefing on this topic, b. At shutdown 1. Begin 4 hout Cause Isotopio analyses and t-elemental analysis for Ni with the technical l 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 Be Np: 3. angin-de8assingfrom15ccjksto43cc/kgH 4 0.03 uC1/gm Re 13 2 .i 3.. 'q,;. iA .q } .y 7..e., y... N m a,.. 70M44
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15 of 36 = '} 11 ace a new CVCP. Nixed Bad in service. 4. ,e 'a,, Draw Gamma !sotopic and B DF samples eyety 4 hours,oron T [i 3 b, ; When Boron DF ise <'10 analysie may 1,' f be stopped, Continue Gam,ma Isotopic analyses until cleanup is complete, q a, c. Cooldown/Draindown gg "3 NOTE 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 domineralisers prior.to H 02 2 addition. I d. Cleanup o 1. When the draindown is complete Hydrogen k-i Peroxide should be added. l NOTE This cleanup will require a l minimum of 60 pints of 4 uninhibited hydrogen peroxide (H 0 I'( : 22 9 l s, f 2. Add 10 pints of uninhibited H 0 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
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\\ n ..D! necessary. dby idzebed in service as ~ ,y . ; * ":i:V. s 9 l Replace used Mixed Bed-as Necessary. Co-58 activity w '9 4 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 system until Co-58 activity is less than 0.03 uct/ga.
- 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 RE-12116 4 RE-11117 RE-2565A RE-25655 ..r RE-25650 RE-002 4.,g" esY
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.e. ngymon . ;,g..,, {. VEGP 49006-C'. " N.2 0-gag so, c \\ '17 of 36 l. i t 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 thermal power, or the reactor is scarced up or shutdown. 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 the Steam Generators are transfarredtotheAuxiliaryEsedvaterPumpa(AFW Steam Generator Blowdown continues in operation. ). 7.1.3.2 If chemicals are not added'to the CST or the reactor has been tricted 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 the Plant is__in Heatup or Low Power operation or Procedure 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 Generators". " Chemistry Concrol Of The Steam e t ,, 3. # se .,y ' 70$448 -,,,..f h' ", w l * * ? W e= i * " w ,e -~~
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7.1.4 Secondary System t i,.- } 7.1.4.1 Prior to a reaching 251 power or after trip,Hyd a can make ches! cal additions of Awoontum and chemistry to the Condensate Storage Tank (C8T) in accordance with ~ r a ne Section 4.8 of Procedure 35250.C, " Chemistry Control of The Condensate Storage Tank". '. t 7.1.4.2 The Heater Drain pumps should be stopped when the Reactor power is below 25! Power. 7.1.4.3 One Main Feed Pump (MFP) is secured below 31 power. 7.1.4.4 CEemistry should request that the~ Condensate and Feedwater systems remain in long path recirculation. If the outage is to be 10 days, Bectinn _4.6 Shutdown - Short Tara wat Larus, of Procedure 35220-c applies. control or The consensate And Feedwater Sys,taas","cneststr 7.1.4.5 If the outage is to be 10 days . preparations for wet lavun of co Chemistry should : ake l ndensate and feedwater systems in accordance dth Section 4.5.2.2 of Procedure 35220-c. The system should be operated with f,ne condensate pump until th3 High Pressure Feedwater L Hesters ar condenser.e 200'F and vacuus 10 broken in the 7.1.4.6 Chemiar.ry B o artment should confira no tube leals in aal watarocaes of the Circulating Water System via Amartap System,-prior to securing condenser vacuum.the 7.1.5-Support Systems 7.1.5.1 l The Auxiliary Boiler-is started below 251 Reactor and l the !$( plant should-be placed in operation. The-Auxiliary 3 oiler will require about 150 spa of makeup feedwater. 7.2 MODE-3 C00LD0VH 7.2.1 Reactor Coolant Syrtes 4 F -. +. ~
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' 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 the accumulators no lonaer require Technical specifica, tion 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". low When steam generator pressure becomes too 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'F of activated co the solubility rrosion products (CRUD inc decrea)ses,reases as temperature which 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 PAQt vo. VEGP 49006-C f 0 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 procedure for Extended Outage a td Section 4.6.4 for a Refueling Outage. 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 are stated in Section 5.1 pf Procedure 30090-c " Chemistry Technical Surveillance Performance Coordination". 7.3.3 Steam Generators 7.3.3.1 below 25 psig, request operations initiate Nitrogen (N ) t 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 be hung on the AuxL11ary Feedwater system urt11 the steam 0,. 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 PAGE NO. ~ VEGP 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 MODE 6 Operations should be borating the RCS to 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 be recirculated in accordance with Section 4.6.4.4 of Procedu made as necessary re 35210-C, and chemical adjustments 7.4.4 Secondary w..
inoctount w .- p.y. m,.n-w. ,i m l.; l am VEGP '49006-C 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. system and Turbine Pla Cu delines for 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 in the flant Extenf;d Life and L. yup Manual. 7.4.8 Radiological Precautions nua l
emoctovat No. _. '.? ~ ngyision VEGP 49006-C 1, nog no. 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 opening the containment for outage work, outags entries Health Physics will establish radiological an,d air quality status utilizing air sample and survey data pada per'RP procenures,in accordance with Section 4.3 radiatio 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 listed in Sectio shall be current 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 the refueling canal in the containment building is flooded, obta 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,g of a unit, lyses on plant vent tritium aan once ptr 7 days it required. I ,e w
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- 1..n VEGP 49006-C 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 per Section 3.4 of Procedure 35180-C, " Chemistry control During Refueling". 7.5.2.5 Place the standby mixed oed in service prior to filling the cavity for refueling. 7.5.2.6 Purification of the coolant via the RRR loop and low l 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 should be plued in service when the Auxiliary Boiler is started up. HOTE (' l During recovery from outaae,be the secondary system should l 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 Pha a VEGP 49006 C 0 25 of 't, 8.1.2.1 N Auxiliary Boiler is in operation. 8.1.2.2 A condensate cump should be running and the condensate polishers are'in 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. Feedwater Pump (Ar8) Discharge - Dissolved l 0xygen t 6 l (
- - e - - - ..m..,, .y NME No-navmon s Paoa wo, VECP 49006-0 '4 0 26 of 36 l-l2, n. _:n 4 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: leakage should be verified by helium leak to the circulating waterboxes. 8.1.3 PERHS Monitor 8.1.3.1 The following PERMS monitors should be available (All HODES). RE-0018 RE-0021 i 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 When a release is in progress via this pathways l t RE-12839A RE-128393 RE-128390 FT-12839 8.1.3.2 The following monitors should be available (HODES 1-4). RE4003 RE-006
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- RsYlWoM PAQt NO, VEGP 49006-C
'y{ 0 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
- 2 out of 3 of these monitors taust be available
. 2565 (A and B) or 25650 must be operable for 2565 to be considered operable. 8.1.3.4 The following Perms Monitors must be available (HODE 1-3) to Change modes. 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 1 specificattor.; are stated in Section 5.1 of Procedure 30090-C Coordina, tion"." Chemistry Technical Surveillance Performance 8.2.3 Radiological Controls 8.2.3.1 Decontamination of Ranctor Cavity l l i
__.---_=--m--- Ag qk.;. pqqg; .-w ~ ~ w, _- h,p 48 f7006-C n. e+ - 0 28 of 36 8.2.3.2 When the Reactor Cavity has been drained, the locked and posted access on too concrete plugs for the Fuel Transfer tube bellows in the Fuel Handling Building and l Containment should 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 Reactor Coolant System should be lithiated in compliance with 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
- y enestnma wo.
~ ~~ esion eAna wo. d VEGP 49006-C 0 29 of 36 If the on-linn monitors are not available, then grab samples should be obtained. 8.3.2.2
- If it is desired to route the Steam Generator blowdown to the environs 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 acc 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 arameters of section 4.7.1 of Procedure 35210-C p' Chemistry Control of Steam Generators" should be, within specification. 7f parameters exceed specification request operations hold temperature and perform correc,tive action to return the parameter en within specification. 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_ .... m p e - moctovna no. r,. namo( ~'T. nog,,o, Y VECP 49006-C ~L , i " 30 of 36 The Steam Cenerator Blowdown Damineralizer a. Chemical parameters are stated in section 3.5 of Procedure 35225-C " Chemical Control Of The Steam Cenerato: Blowdown Processing 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", The secondary plant should be operating in long a. 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.
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'eAos no VEGP 49006 C 7 0 31 of 36 1. Individual Polisher Bed Effluents i Cation Conductivity a. b. Sodium 2. Combined Polisher Effluents 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 Samples dwater system, ' 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 Prior to Mode 4,for the In-core Detector driveoporation i on the breakers motors so they cannot be operated, t 8.3.3 PERMS 8.3.5.1 The following monitors should be available prior to 250'F. RE-12839A RE 12839B RE-128390 FT-12839 f h 4 m* c. L- ,+1.ws.n~ M L"'-
. - w... 4 PMoctDW u No. 'Y.. mayassou proTWo-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 and PZR for dissolved oxygen, which must be less than 100 ppt 8.4.1.2 When PZR heacup begina and saturation temperature is reached service., place the PZR steam space sample line in 8.4.1.3 Between 300'r and 330*F RHR is isolated and cooled down. 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 monitors are not available, then grab samples should be obtained. 8.4.3 Secondary System 8.4.3.1 Place the CST in o dissolved oxygen. peration, hemical parameters shouldChemis The CST c be within specifications started in Section 4.5 of Storsge Tank". Procedure 35250 C. " Chemistry Control Of The Co 8.4.3.2 Above 340'F the Auxiliary Faedwater pumps will be placed 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 Put wo. O VEGP 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 Section 3.3 of Procedure 35160 C. " Chemical control of the Accumulators". i 8.4.5 Radiological Controle 8.4.5.1 350'F.Re-establish flow throu8h RE-48000 prior to exceeding i 8.4.6 PERH8 8.4.6.1 The following monitors must be available prior to NODE 3: 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 in Table 4 of Procedure 35110 0 are not within the recommended guidelines. be place on the volume control tank.Rydrogen cover gas should Chemistry 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 On8tartupIonsskouldbemet the specificat over operation i prior to exceeding 301 power, this allows action level 1 values in Unit Startup to 301 power. 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 for greaterthan51 power,arelistedinSectiond.8 _ Ops. Condensate System and in Section 4.9,_ Power, F { Power feedwater System or Procedure 35220-0, "Chemicat j controt or condensate And Feedwater System". 8.6 HODE 2 TO H0DE 1 i l Reactor Coolent System l 8.6.1 ') i thermal powerIf there is greater than a 151/Hr redvetion in reactor l 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 specifications of Sections 4.7.4 of Procedure 35210-0 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 Section 4.7.4.2 of ; Procedure 35210 C.once per shift while ramming up in po 8.6.3 Secondary 8.6.3.1 At 41 power, form Auxiliary Feedwater to M i a MFP is started 8 team generators transferred re one steam generator at a time. a n Fei.Jwater n...
~
PROCsDURENO,
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AgYitioN 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, Prior to Ope a. drain pumps, rations department starting the heater samples to verif the chemical parameter of the system shoul be taken 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 monitors are utilized for indication and must f 1 either be available or grab sampled must be taken, i The following On-Line analyzers should be in c. 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 in the ammonia form, at the discretion of the on shift chemistry foreman. 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 PAQt No. VEGP 49006-C 0 36 of 36 [ 9.1.4 12001-1, "Unic '.feating To Hot Shutdown (HODE 5 To MODE 4)" 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, " Unit Cooldown To Cold Shutdown (HODE 3 To HODE 4)" 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, " Chemistry control of The Refueling Water Storage 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 Physics And Chemistry Department Outage Activities" END OF PROCEDURE TEXT mu s ~ ~~ -}}