ML20024B893

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Guide for Preparing Nuclear Plant Operating,Emergency & Maint Procedures
ML20024B893
Person / Time
Site: Crane  Constellation icon.png
Issue date: 08/31/1968
From:
BABCOCK & WILCOX CO.
To:
References
TASK-02, TASK-05, TASK-2, TASK-5, TASK-GB GPU-2311, TRG-68-62, NUDOCS 8307110734
Download: ML20024B893 (65)
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) L *. -~ :- ~ ~ E; p t EiN TRG-68-62 August 1968 Nf. - _-4 __E) m*. I' CUIDE FOR PREPARING NUC LEAR {7 PLANT OPERATING. EMERGENCY, AND MAINTENANCE PROCEDURES

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f t g rg v. {.~'[ CONTENTS %jf 1. IN T R O D U C TI ON.............................. 1

2. SC OPE OF PROC ED UR ES.......................

2 I g 2.1. Genera1................................ 2 2.2. De fin i t io n s............................... 2 - -*1 ' 3. D ESC RIP TION OF P ROC E DURES.... '.............. 4 R.C . _. ~ 4. A DMINIS TR A TION............................. 5 (Q j 5. RESPONSIBILITY AND SCOPE OF SUPPLY............ 7 i - f 6. RELATION OF PROCEDURES TO OTHER -g "_ DOC U M EN TS............. :.................. 8 g.', 4

7. SCHEDULE.................................

9 w -M APPENDIXES A. Procedures Prepa ration Schedule.,.......... A-1 B. Nue!ea r Plant Procedures outline............ B-1 Id'4 C. AEC Letter Concerning Conversion of Provisional to Permanent License '..... C-1 D. Startup From Cold Conditions.............. D-1 t h E. Filling and Drainir.g Fuei Transfer Canal....... E-1 l e4 F. Core Flooding System Operating Procedure..... F-1 l ...Cu _ Q pk C.6 a, 1 l f j 1 - in - Babcock 'witcox, ,~ f, a.0 C t,19 5 9 8.

~.,. .l ~ 1 4 W l. INTROD1*CTION D Formal procedures'have been used in nuclear power plants since Q their inception. The depth of such procedures increases rather than decreases with time as the nuclear plants become more sophistica:ed. The formal requirement for opera:ing procedures and administra-g tive controls is contained in Section N. Appendix A, to 10 CTR 50, in ~ which technical specifications have been required to describe the avail-M ability of detailed operating procedures and the manner whereby opera-ting procedures are reviewed and approved for use. This subject is also covered in the proposed revision to 10 CFR 50, See: ion 50.36, dated August 17, 1966, and in recent AEC letters to plant owners who are converting a provisional facility operating license to a permanent license. The text of this letter, with empha. sis added to portions c=ncerning pro-g cedures. is in Appendix C. This guide should be used in conjunction with B LW's guides.2 in order to integrate :hese three essentially concurrent 8 and mutually dependent actisities One of the most significant nuclear plant cocuments sill be the ~~ ~ ic~ch'nical Specifications, which are part of the operating license. Op-M eration of the nuclear plan: in a safe and efficient manner withou: exceed-ing plant Ilmits, as defined in :he Techmcal Specifications, is a key re- ,M quirement of the opera:ing procedures considered in this guide. S M k- .4 M. 'Ouide for Planning and Executing the Nuclear Plant Field Testing and Startup Program. at.: Duide for the Organization anc Traimng of the Nuclear Plant Staff. n Babcock & Wilcox 1 .g. ~w._ ~ L a.0 ?C ~ W599' L t

~. -.. ij 4 ~ :- -e. c-I J l J 2. SCOPE OF PROCEDt*RE5 2.1. General This document presents a preliminary outline of the procedures to be provided by S8.W* for the nuclear plant. Changes will occur as designs are completed and. specific components are selected which require pre-1 Also included in the outline are some of the procedures cedural changes. required for the balance of plant..which the plant's owner will include 4 as desired. or required by commitments to the regulatory agencies. The outline is flexible enough to allow modification to fit the o.wner's normal practice. For instance, each rnajor subdivision of the procedures outlir.e may be a separate book or volume. The procedures numbering system is chosen to be compatible with a computer program used for administrative control of issue and review, and the system can easily be modified for the final plant procedures to, conform with the owner's f normal practice. I 2.2. Definitions ^ l Several terms are used herein which are defined below to avoid j ambiguity later.

2. 2.1.

Draft Procedure This procedure gives essential limits, precautions, major starting and securing sequences, and operating modes in order to re-main within the design envelope. Valve-by-valve, switch-by-swsteh rout.nes needed by an operator to execute the procedure are not included unless tney are mandatory for c!srity. 2.2.2. Om ratine Procedures All normal operations expected in the plant are documented as operating procedures, which define the detailed steps, limits, and Babcock & Wilcox 2 l =.. c _. ~ s [ LC +C p., i o c: I

j ~ r precautions to be followed by operators in ope rating their plants. P rep-( aration of these procedures (including emergency and main:c :ance pro-l cedures) is the plant owner's responsibility. BLW provides drafts, as defined above, for the scope of supply. 2.2. 3. Emergency Procedures '_p Potentially hazardous conditions that can occur, but are (k f not part of the normal plant operating sequence, are covered by the emer- _Y gency procedures which provide for recovery. safe shutcowTi. or mini- { } mization of the potential hazard. 2.2.4. Maintenance Procedures s As intended in this guide. the maintenance procedures %h. place the plant or system. with appropriate overall limits on plant op-eration, in condition to execute the detailed component maintenance pro- 'o .. I cedures found in the technical manuals. 2'. 2. 5. Procedure Verification ~ v.-g -f - A procedure is used during the field test and startup pro-gram to ensure its validity. Where necessary, such verification may se be included in a field test. -j, _r- .e [.i_ 3 'Na A b 3. .s _ s 1 d --T .U LJ .s**a. ~ I x . ] Babcock & Wilcox 3 i M _a ~ [a.O l+G \\9b o 4 e l

1 1 1 3. DESCRIPTION OF PROCEDURES 1 In addition to the outline of nuclear plant procedures (Appendix B), examples of draft procedures are included which will be prepared or modified as necessary for a specific plant and application. Pe r ins tance, under the operating procedures for the reactor coolant system, an ex-ample of the draft procedure "Startup From Cold Conditions"is given (Appendix D). Appendix F is an example of an auxiliary system draft s procedure for the Core Flooding System. A final specific example of a draft procedure is presented in Appendiz E. Administrative procedures, such as emergency plans involving off-site agencies, procedures for the control of plant maintenance, quality control, etc.. may be included as chapters or sections of the manual as desired by the owner. . I 5 .4 eq g. t Y , Babcock & Wilcox ,4, T L. , a.0 4-E @ e o r u r V

~_ _.-_.~2._.. t 2 s o ye ) 4. AD'.!!NISTR A TION" The sequence of prepa ration for these procedures is as followst w 1. Set scope of procedures. '2. Prepa re procedures index. M 3. Prepare schedule for issuing procedures. 4. B&W prepares preliminary draft procedures for B&W scope of supply. 5. The owner reviews and comments on B&W's draft. 6. B&W issues a final draft procedure. Owacr-originated procedures directly related to operation of the NSS 1 T.4 m!! be reviewed by DLW in a similar manner. Submission, review, and completion of the diaft procedures will g be handled in a manner similar to that used for field test specifications. ~ As this work proceeds,' the explicit listing of procedures for the plant will be included in a Test Spec / Procedures In'dex. which is a computer-g' printed !! sting devissd to minimize administrative burdens. Unresolved questions concerning these draft procedub Ull be reviewed at meet. b ings of thic Test Working Group. In this connection, it should be noted that most operations during the test and'startup program will, of neces- ~ (.#i sity, use the plant operating procedures.. The adequacy of procedures ~' will also be verified during the plant field testing and startup program. pg At a time consistent witg the o'perator training program and the field test program, the pros'pedtive plant operators will prepare detailed ~ N step-by-step, valve by-valve proc'edures for use in the plant. The d ra f t f*g I procedures outlined herein will be usegas the basis for these procedures. The Ia'tter phases of this activity should be executed at the plant site as b a significant pa rt of operator on the-job training and plant familiariza-tion. ?s Q y"4 7-Babcock & Wilcox -s- _.-w-l a.0 %

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L e s ^ Of interest is the amount of time and effort required to prepare the plant procedures. No one specific statement is possible because of ~ differences in the plant owner's practice, previous experience of person-nel, and varying scopes of supply. As a minimum, it is estimated that 3 to 4 man-years of effort will be required to prepare the plant owmer's t i scope of plant procedures. Approval of procedures for use in the nuclear plant is covered in the Technical Specification submitted by the plant owner along with the i operating license application. In general, this involves review by a Site Safety Committee and approval by the plant owner's Nuclear Safety Com'- mittee. 1 1 i i I i i l I .i J l [ 1 l I Babcock & Wilcox. 1 i l I l \\.------ a

P .4 .j _ /~ Q F J 5. RESPONSIBIL:TY AND SCOPE OF SUPPLY M* The procedures outlise lists the parties responsible for preparing W each procedure. If there is no ambiguity, responsibility is assigned to either B AW or the customer, or both. When va riations a re possible be-3# p cause of the scope of supply, responsibility is unassigned. The Test g Working Group will make specific assignments consistent with the scope ~ of supply, The procedure outline given in Appendix B wi!! be computer-printed W.J as part of the plant Test Spec / Procedures Index when the scope of the E3. contract is set. nd w o

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f 's 1 a._ i ~ E 1 I 6. REl ATION OF PROCEDURES TO OTHER DOCUMENTS i The basic documentatior. for the nuclear plant includes SAR. draw-sags, design descriptions. field test specifications and procedures, op-erating procedures (including emergency and maintenance procedures), BLW and vendor instruction books and manuals, and plant technical spec-ifica tions. These operating, emergency and maintenance pro'cedures must be consistent' with the design and licensing documents. These procedures prepare the plant for component removal or re-placement and for maintenance as specified in the technical manuals. l In addition. the procedures account nor the simultaneous appucation af various limits, imposed by design documents and provide for the transi-tions from one state to another in plant operation, s i y s l l Babcock & Wilcox 8-6 8. 4." "em ai 2.0ifQY960t ^ e ,m

f -- m.. a..._,.. x _ W C1 l \\p-7. SCHEDU LE Appendiis A show;s the relationship between key events in the plant schedule. training schedule. and these procedures. The preparation of these procedures depends on the development of basic engineering infor-M mation for the various systems. The procedures must be completed in time for operator on-the-job training at the site and operator license examination. Completion is also required to permit performance of the _ as test program and verification of the procedures during the field test and startup program. As shosm in Appendix A. BLW's draft precedure will be prepared over a period of approMmately 18. months, in conjunction with the pt'ep- .N aration of the field test program. The plant ommer's scope of procedures should also be prepa red during this period. 'M A computer-printed schedule for issue and renew control during preparation of the test program and operating procedure is available, This may include procedures originated by the owner or BLW. The issue g schedule must be based on the plant schedule and the engineering schedule. The Test Working Group will schedule this activity. a g l [% \\. F3_ W]R FM N f5 0 t f'R ? :. ' ~ bx Babecek LWilcox ,9 f 5 10 tl-C dy60?! ~ I i

f $s-n G JQ o NL 9ae APPEN.DtX A Procedures Prcpsration Schedule a Q .Ws -~ ~ a .45 . M. Um b.a l A Babcock L Wilcox .s A.3 l E

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..--.--....~%. .... ~, ~, l j 5 J 1 ) q i i 1002. INTRODUCTION 2003. DEFINITIONS 1100 OPERATING PROCEDURES 1101. Limits and Precautions

02. Plant Operating Procedures
03. Reactor Coolant System Operating Procedures j
04. Auxiliary System Operating Procedures
05. Instrumentation and Control System Operating Procedures
06. Steam System Operating Procedures
07. Electrical Systems Operating Procedures 1200. ABNORMAL AND EMERGENCY PROCEDURES 1201. Symptoms of Abnormal and Emergency Conditions y
02. Plant Emergency Procedures i
03. Abnormal Plant Procedures NUCLEAR PLANT TEST AND' INSPECTION PROCEDURES 1300.

j l 1301. Frequency of Tests and Inspections

02. Plant Calibration Procedures J
03. Instrumentation Calibration Procedures
04. Periodic Test and Inspection Procedures 3

1400. MAINTENANCE PROCEDURES 1iot. Reactor Coolant System Maintenance

02. Auxiliary System Maintenance
03. Instrumentation and Control System Maintenance
04. $ team Syste m Maintenance
05. Electrical System Maintenance j

1500. REFT.*ELING. P ROCEDURES 1501. Limits and Precautions a

02. Refueling Ope: ation. Sequence of Events
03. Preparation for Refueling
04. Closure Head Removal and Replacement l
05. Reacto.r Internals Removal and Replacement During Refueling
06. Tuel Hand!.ing
07. Incore Monitor Handling During Refueling
05. Tailed Tuel Detection and Handling
09. Neutron Source Handling
10. Spent Tuel Shipment 1600. RADIOLOGICAL CONTROLS 1601. Limits and Precautions I
02. Monitoring Procedures
03. Radiation Monitoring System
04. Decontamination 8000. TIGURES

'l 9000. RETERENCES Babcock f. Wilcox B-2 7m 7 9 LLC

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~ ~ s. I ~ ,-) (Y_ h,. 1002. INTRODUCTION Procedures are ini:1uded for the Nuclear Steam Supply System, its -4., auxiliary systems, and associated instrumentation. The rest of the plant h system procedures are indicated for inclusion by the customer. Proce- ] .'_ dures are written from the point of view of the console operator for'over- {~,] all plant procedures. Individual system procedures require on-scene /' local operation. Component operating procedures are found in compo- { ;} nent technical manuals and are included herein only to the extent neces-g sary for clarity or when sequence may affect the safety of personnel or equipment. @p. ~ Sections 1100 and 1500, operating procedures and refueling pro-cedures, are arranged in order of normal use except for operations that b can be performed independently of the main sequence. ( Each procedure is based on initial conditions being met. The use {j of a procedure out of sequence or without verification of required initial 'l conditions could inadvertently l'ead to abnormal or emergency situations. When si:uat.ons arise that are not covered by these procedures. a pro- .~ cedure should be w ritten ba sed on plant limitatio' s and precautions. n technical specifications, and evaluation of the situation. _ d'.%- Immediate corrective action in the emergency procedures is based on the worst condition possible. Thus, a high-temperature alarm on a component assumes overheating rather than temperature detector mal-h A. function. Action required by the condition should therefore be carried out unless immediate verification of instrument failure or other condi-g tions is available. l1- + n M. 33 Babcock t. Wilcox 4 v var--- c -en m,

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s ~. 1003. DEFl$1TIO[S ~ ~. OPER'ADLE . System or component is ca'pable 'of'p'criorming all de-... e +.. signed functions. . % d: " IN SERVICE *;&.';Si..stAm is. operable arid in us,e.. w > 7,

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SHUTDOWN..t;a n.. en 'rgize'd and fully.inseried. Baron concentration is -.'s-at or above that required for specified suberitical mar- ~: gin at the exisiing. reactor. coolant temperatdre and ~ 'h core lifetime.- t i In the' event stuck (ou.t)'rodi exi.s.t'. b6ron concentration 3 has been increased by an amou'nt required to cornpen-sate for s, tuck' rod (s)., v. STARTU,P Control' rod ' drives' a ri en'ergized:4sence, control. rod ~.. motierris possib!'e'.dr in progress. Any intermediate ? condition betwe.en shutdown.trid efitical. in.cluding testing *of control r'od drises wiih.~to intent of taking r reactor critical' : [.;. ' ^ Intent of definition is t'o requife minimum ' safety sys-tem and. safeguards rea<!iness a'ny time reactor could become critical because of b.eing in a ' start 6p condition. PRECRITICA L A comprehensive procedure involving functional testsi CHECY. alignments (of instruments), system.!!neup che. ks, c and administrative procedure.t'o ensure safe sta r' tup of the reactor. This forms part of the overall plant sta rtup procedures. Extent of checks made for startup depends.on length of shutdown, work performed, ar.d reason for. shutdown or trip. Babcock & Wilcox 34 e s 2.0 4-C [fo 6 J 's! ', .m_h ,:f-s.

. ~ , -.:~---------.--_-. CRITICA L Neutron level is steady or increasing (above shutdokn V' level) with no rod motion or boroh dilution in pregress. E,j' ' FUNCTIONA L Use of built-in test devices (instrumentation) or built-TEST in test capability (Decay Heat System recirculating utf' line) to demonstrate operability, function, and for in-strumentation alignment within specified operating tolerance of readout or cargtrol actions. A LIGNMENT Use of internal or external test signals to make adjust-ments to module, channel, or instrument string for Df.- readout, output. or action within specified tolerance. CA LIBRATION Use of standards to align module, channel, or instru-b ment system from sensor to readout. output, or re-quired aetion within specified tolerance. Calibra tion Q of sensor may be independent of system alignment and provide data which are then used to complete system - alignment. '\\ { {- TEST A generic term which includes Tunctional Test. Align- ?- ment. Calibration. Periods.e Tests. Physics, Tests. and others. (: _5 - - ~ ~ - - - - - ,,e - ~ ~. _ L4 en pq sse l'., N a b3 rk l P ~~l g,-. Babcock & Wilcox B-5 r 7 . _ 2vq a.O lff j96ff p

1 ~ 1100. OPERATING PROCEDURES i 1101. I.imits and Precautions 1.imits and precautions contained in this section are for overall plant control. I.imits applicable to individual systems or components which are not observable or controllable by the reactor operator are included under system and component procedures or in component tech-1 nical manuals. 3101 01. Reactor coolant systens pressure versus BLW a temperature limits. NDT, irradiation BLW Reactor coolant leakage limits 1101 0?.. Known paths Unknown (preaccident consideration) 1101 03. Heatup and cooldown pressure and rate B&W limits 1101 04. OTSG shell-to-tube temperature limits B L%* (mass weighted temperature difference) 1101 05. RCP operating limits (RCP motor limits by customer if not B&W ' ' " ~ - supplied by BLW) Pressure (NPSH) Tempe rature Seal w3ter Cooling water restart limits S ta rt, Number of pumps required or permitted BLW 1101.06. CRD operating limits Min / max pressure L temperature With dropped CRD With inope rative CRD' With misa!!snment within group ~ CRD positson limits at function of lifetime. power, boron concentration / 0 ? Babcock & Wilcox ! B-6 e I e-c' 2.0 4-C &415 { L.:

..y... . 3. CR D motion Izmits while shu' einwn 1101 07. (nuc! car safety) .B &W 11 0 l' 0 h. Reactor coolant boron concentration vermus temperature for If. shutdown versus. rods inserted BLW I101 09. Manirrium systems and components in B LW k service for operation or startup Customer k.i.. I101 10. Minimum systems and component in. B &W L ' KW mervice while shut down Customer 4 1101 11. Mimimum instrumi*ntation for: B AW k. T Customer..^ ,4,; - Star p . f b. 1101 12. T:.ak levels for ope ration and startup B&W L.II Y {'] (including'Isoron concentrations) Customer '-{ y Y 1101 13. Radiochemistry specifications and' activ timits-from chemistry-. Gross activity [.- ] Fission product activity (include pre accident limit) ,7

  • .A 1101 14.

Total gas L hydrogen limits in i reactor coolant system-from l chemistry manual B&W g During operation Before depressurization 1101 15. Reactor power. temperature, and prennure limats (DNB) BLw d 1101 16. Limst= un reactor critical op. ration in subpomer range SLW \\- ch.' 1801 17. Reactor vessel water level BLW F* e.% 'N, j. - - 1101 18. Syphoning precsutions, reactor coolant system BLW g -3' 1101 10 Containment integrity and access Ismits Custome r fk Ope ra ting Hot standby Shut dnwn & cooled down b, RC system open to buildirg atmo*phere (refueling) Babcock & Wilcos B.7 S ~. "-. t

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--r.e=:.,J.;;,w e.q, L10110.',. Limitations on use of decay heat -. i ~ c .2'%t-3LW A.l?2 d;;. __ - removal aystem. W p p.-c :. u.,,.{.5. $ w...:.r c Decay heat rate F I. V '" \\ wwwc.. ~ ~ s 9...*(2 's v*.-Qio J.. i. P re s s ure a nd te mpe ra tu re.~ Decay heat syst Mw4{... v. ..mi,..,. ~ i .u Custome r I 'g 4 -ff. Rf&f;4.%,%~M'f.a.a, ~. Availatility of e;lectrical power.. l y.M:74*M._._.^cy tg_01,,21.2 t.,.. -L1 s.v. g. ,g:s a. Ope rating.,, %. -t. < k, I wr:2gtg<.:m. Wg. l ea J dby.. - '_p n.-..;t.As,..J.a. Hot stanq. 3.k. Shut down and. cooled down w-w..:::: L, w = c.. 2 . Reactor coolant system open to u.. . W m J ea: C M., e- ...i..%... V....- atmosphere. ,p n ..~N.;g,n.. -:.~..,.M.m,;.

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Customer q; - 4~.g ca ;. 0. '. 110123. Turbine.-generator limits ~ r e,..c[..re e.,((f:+.,4;[(.'y.- Vibration 4 . +. 'w v.. < }. 5P**d g ;.' ::.id$' s'k'.L....~ ' , Va cuum

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h = ,Y p5 ..f'*P O... s..p's. j Bea t.r; Et temperature T-@.. r, yw~. a. "j t.- Minimum steam flow (power)'for - sf;. %['e' .' P'. 't-:' turbine cooling maximum TG . M 75" 3 .'.M"...' loading rate -c:.. . y.c,-, !.:. l'. Exhaust trunk ternperature j TG,- Thrust bearing failure (rotor position) 4':. NO.-5.. r! ;..... Differential exP"nsion 7.W T Phase differential DLW L ~ g,. y,.q-u...... h,';. 47 \\. J' ,up!v. - -l WI " 1101 14. Feed system Ilmits Customer .M3.n P re s s ur.e A.'6 Tiow' Minimum feed temperature 3 Emergency feed system hmitations Feedsater chemtstry limits at:d specifications-f rom chemistry BLW manual BLW 1101 15. Steam generator limits Wate r level l Temperature j Pressure (s econda ry to primary.1P) i Sa'bcock & Wilcox B-8 _ _. = 1 ' 10 F 1.061.7. p c

....,...~....._..........?.;::,,___.,._,... i ... -.. 3 I i 1101 26. Reactor power limits RCP trip or unavailability ~ .} Teedwater chemistry upset Excess OTSC fouling .) S. Control rod drop or misalignment Turbine trip Teed flow (loss or partial loss) L.. J l oss of generator stator cooling Xenon oscillation' -..] Xenon override Turbine stop valve testing ! oss of controlling NI channe! OTSC tube leak {,.~ 7 'f. Reactor chemistry upset Minimum turbine / generator load Bypass load limits Nr.. !!01 27. Power rate Ilmits Turbine loading limit -g q.- a,* GA Turbine temperature limits Reactor limits - {~. j _1l_02. Plant Operating Procedures - Y . -r-Plant operating procedures are arranged in sequence for normal F..- 3]- startup from cold refueling or maintenance conditions to power opera-J <"* tion. b.9 Each individual procedure assumes that required auxiliary sys- ~ _. 9 _ tems and services are in normal line up opin service. When startup F. ] of an auxiliary system is required other than by actions at the reactor _'vr.y operators console, the needed procedures are found under system op-erating procedures. J Each operating procedure contains the fo!!owing sectionet l t., - s 1. Purpos'e 2. 1.imits' and precautions .t.g 3. Initial conditions {-] 4. Operation (procedure) - 3 ' V' b3 5. Final conditions 3 1102 01. Plant precritical check B&W k Custome r !!02 02. Startup from cold conditions BLW L Customer ,k l Y 6. Kh Sabcock.& Wilcox 7] B-9 I l a.0 46. @i 6 1 81 s. l

.z.c. -l. ~' 1102 03. Startup from hot conditions BLW k Customer I102 04. I.ow power operation 3LW L Customer 's 1102 05. High power operation BLT k Customer .9 1102 Co. Ste.ady state power operation BLW L Customer 11D2 07. Xenon transient override BLW L Custome r y 1102,08. Inc reasing load B LW L Customer

]

1102 09 Decreasing load SLW L Customer d, .' S 1102 10. Shutdon: 2 Turbine Customer .g BLW Reactor i 1102 11. Cooldown BLW t SLW 4 !!O2 12. Dega sification 1102 13. Decay heat removal ELW _1102 14. Reactor building purging and Customer venting .J ..) 1102 15. Till and drain fuel transfer canal BLW i I l 1103. Reactor Coolant System Operatine Procedures Reactor coolant system operating procedures include a!! norma! ~" evolutions needed to support overall p* ant operat:ng procedures. Also included are procedures for wa.cr level pressure, and temperature cor. trol which a re required for refueling and maintenance. 1103 01. 1103 02. Tilling and ven:ing reactor coolant BiW system Tilling and venting instrumen: lines SLW ~ Babco & Mcox B-10 i t 10 - -

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. ~...,. g. G3 1103 03. Hydrostatic and leak tests BLW l CRD caps Head seals j Reactor coolant system !!O3 04 Soli:ble poison concentration control B&W y. Refueling Maintenance Sta rtup Power operadon Shutdown 1103 05. Pressurizer operation B&W Forming bubble 1103 06. Reactor coolant pump operation BLW L-1103 07. Reactor coolant pump heatup B&W bh ' !!O3 08. Approach to criticality, B&W 1103 09. Critical heatup BLW 1103 10. Starting and stopping reactor coolant {] pumps at power BLW (T 1103 11. Draining and purging the reactor . B LW L I coolant system Cus tomer , M.. For refueling For steam generator maintenance For RC pump maintenance ? For pressurizer heater replacement t s. ' " ~ 1103 12. Steam generator chemistry control BLW 1 1103 13. Reactor coolant system volume and .D purification control BLW A. !!O4. Auxiliary System Operating Procedures These procedures each include the fo!!owing sectionst ,N, \\. System lineup for normal reactor operating y 1 ]c,onditions

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s e . W or I 1 j Operating procedures include the aux 211ary systems instrumentation op- .h ersting procedures. B&W. 1104 01. Core flooding B&W 1104 02. Makeup and purification 3 1104 03. Chemical addition and sampling BLW J 1104 04. Low pressure injection and decay heat removal (decay heat removal) .B&W Decay heat removal operation B&W 9 1104 05. Reactor building spray 1 B&W 1104 06. Spent fuel cooling BLW 1104 07. Waste disposal i Resin sluicing Waste evaporator Component cooling (intermediate 1104 08. 2 BkW cooling) 1104 09. Recirculated cooling water

  • Customer 1104 10.

Low pressure service water

  • Customer

~ 1104 11. High pressure service water

  • Cus temer Customer 1104 12.

Condenser circulating water 1104 13. Demineralized water

  • Customer 1104 14.

Reactor building ventilation Cus tome r Customer 1104 15. Reactor building cooling system Customer 1104 16. Penetration room ventilation Cus tomer 1104 17. CRD ventilation Custome r !!04 18. Reactor building purge 1 l Procedure ns.mes should be selec'ted to fit plant nemenclature. Babcock & Wiless 3-12 e ,e-

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v [Y 1105. Instrumentation and Control System Operating Proerdures Instrumentation and control system operating procedures include

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those operations beyor.d the scope of the technical manuals for the sys-tem. These operations are those affecting overall plant control. N 1105 01. Nuclear instrumentation B&W !!05 02. Reactor protection system BLW M- !!05 03. Safeguards actuation system B&W e 1105 04. ' Integrated control system BLW Reactor control Steam generator contro! .y Turbine control ~ !!05 05. Incore monitoring system BLW N 1105 06. Reactor nonnuclear instrumentation B&W I105 07. YK Radiation monitoring system Customer 1105 08. 3,x 1105 09. Control rod drise system BLW I. - 1105 10. Compute r - . Customer ~~~ '~ ~ ~ ~ 1106. Steam System Operatine Procedures 1106 01. Turbine generator Customer k,*. =. .3106 02. Condensate system Customer IId6 03. Teed system B LW L .f. ;R ^ Customer I.106 04. Auxiliary boiler 'Cus tome r d. 1106 05. Turbine bypass Customer f.y 1106 06. Emergency feed. B&W L Customer DS !!O7. Electrical Systems Operating Procedures (by voltsee or function! ~ je.f 1107 01. Reactor coolant pump electrical Customer p. 1 B-13 sabcock a witcox e ,w-a Oe ( a.0 % ji2 @ ? ?> 1 l

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l _] = } 1200. ABNORMA!. AND EMERGENCY PROCEDURES, h f.? Y. 1201. Symptoms of Abnormal and Emerrency Conditions {% 1. Abnormal or emergency conditions are disclosed by: (,.' a. Departure of instrument readings from normal. b. Lack of agreement between redundant instruments. c. Calculations showing inconsistency, such as dif-E~c .7 y,4A ^ ~ ferent results on reactor primary and secondary heat balancee 3;c. 4. .d. Ala rms. p. g. e. Visible and audible indications such as leaks and e T* _ sound of machinery in distress, e Z. Table 1200- t o which follows lists symptoms of emergency h-conditions and alarms in approximate order of urgency. The e b.< symptom or alarm is fol!os.ed by set peint or normal value s immediate corrective actions and possible cause. When a Q-specific procedure applies, it is referenced. E_.] ~~ r* p Table 1200-1. Symptoms of Abnormalities and Emergencies U-- fg-se,,-ei oi.e, t_ece,e,e,,e,- vesa.we l s_..,p..ge re,- ee, e..e. e..is. ,e.e e. e. ,eeee e. ~ sC prese.e. 21SS 3. Chece ask pressure R upt ure eF !.m e te rm i L. 2. C hec h P C.**. Leek 5. chese Mc temp

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Res taseresen f ens entrollee 2S$3 8. Verts,reerser - E.d.. R.eestar tese x* .e. p..e..... ,,,s.. 2. Vertiv *ettane pe IFBpeed I. Checa RC pressure a 7-.; yg Re ;ew1. terny E_ _ Step L D 4 7.re oc keerets j i A-

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~ ~' - ..^ ..s e 'n 1202. Plant Emercency Procedures Plant emergency orocacures assur9-cor-act instrumen' indica-2 tion and a worst case for immediate corrective action. Where an us..lcr- ,] lined symptom 1s known. Immediate corrective action is mandatory to i prevent further personnel or equipment hazards. In a case where an automatic action should have occurred. such as r.eactor trip, it la in-cumbent on the operator to manually initiate the action. Each plant emergency procedure includes the following sections:

1. Symptoms 2.

Discussion (possihte causes) 3. Immediate action 4. Followsp action 1202 01. Load rejection (blackout) B &W L Cus tome r l'202 02. Turbine trip. BLW L Customer 1202 03. Turbine overspeed Custome r 1202 04.- Reactor trip BLW 1202 05. Reactor high startup rate B&W 1202 06. tJnexplained loss of reiactor coolant: BLW Leak Relief valve lift OTSG tube leak Rupture l High pressure in letdown piping. LD storage tank demineralizers 1202 07. Loss of boron (moderator dilution) BLW 1202 08. CRD's fall to respond ELW 4 1202 09. CRD mevement improper BLW 1202 10. Dropped control rod ELW 1202 11. Hsph activsty tn reactor coolant BLW Cros s activity Tiss son product activity Babcock & Wilcox 5-16 s... LCL!-C gf0 6 2 E g e l L L-l \\

^ ~; l p. i e'.. 1202 12. High radiation levels Customer Reactor building er-Auxilia ry building 1202 13. High station vent activity Customer 1202 14. Loss of reactor coolant flow B&W 4 RCP trip 1202 15. Loss of reactor coolant makeup BLW s;ot 1202 16. Loss of seal water BLW h. RCP N_ fI CRD h.5 ], 1202 17. Component (inte'rmediate) cooling if system failure BLW W& m2r ~' 1202 18. Recirculated cooling system failure

  • Custome r wg 1202 19

'bw pressure service water system failu re" Custome r .na r c. t- \\ 1202 20. High pressure service. water system _[ .ner failure

  • Customer lW b-.

g.4.f. 1202 21. Condenser circulating water system ILW 7' failu re Customer k;p,7 ~ ~ 1202 22. bss of condenser vacuum Customer ggy 1202 23. Steam cenerator/ feed / condensate Customer. g, High salinity or conductivity p 1202 24. Steam spstem leak / rupture .BLW .e'.h. 1202 25. Feed system leak / rupture Cus tomer 1202 26. Los s of SG feed BLW 3, lLW 1202 27. Dry steam generator BLW 1202 2A. Reactor component high temperature BAW [j'N RC pump and motor ILW CRD L, tLW Letdown fk .LJ ~ g Cooling water systems should be named based on indindual plant design. A. ,D B-17 Sabcock & Wilcox = e9,'-' - -- [;. O-j

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j r 1 a 4 13229. Pressurizer spray valve failure (open. closed) B L%* a 1202 30. Ea rthquake Custome r 1202'31. Fire Customer 1203. Abnormal Plant Procedures Abnormal plant procedures may be used during equipment mal. function with otherwise normal plant operation continuing. The plant may be started up ir. tending to use these procedures, or the equipment malfunctson or outage may occur during operation. Each procedure as. sumes the latter, which is generally the more demanding condition. The procedures contain the following sections:

1. Symptoms 2.

Discussion (of causes) 3. Procedure (action to be taken)

4., Operation (in abnormal mode)

^ 5. Restoring normal operation 1203 01. ICS abnormal operations BLW Manual reactor control Manual feed control Manual turbine generator control 1203 02. Reactor coolant system abnormal BLW ope ration ~ Manual pres surizer level and' makeup control Manual pressure control Idling a steam generator Returning idle steam generator to service 1203 03. Auxilia ry systems abnormal operation B L%* 1203 04. Turbine generator abnormal operation Customer 1203 05. Feed system abnormal operation Customer Babcock Mcox B-18 ~ y.z u._ m 10u-3.0 6 2 7 4 y s 1

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~ a a. n. l. 1300 NUC1. EAR PLANT TEST AND INSPEC"UON PROCEDURES g Nuclear plant test and inspection procedures include inspections and tests carried out while operating, shutdowis, after repairs or refuel-g ing, and as pa rt 'of planned preventive mainter.ance. Tests (which include alignments. calibrations, functional tests, periodic tests, physics tests, etc.) are those necessa ry to ensure plarit integrity, operability of sys-tems and safety devices, and those required by facility !! cense and good engineering practice. 1301. Frequency of Tests and Inspections Requirements for tests are shown in Table 1300-1 and for inspec-tions in Table 1300-2. This section covers test and inspection procedures which are' hot included in compor.ent or system technical manuals. M Table 1300-1. Required Tests Proced.re (J' 'sv. tem eem e, reecreou rew o N tea, an.tr mentata

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reecy r.n i 8 MZ M pese r da y. At first pe=er eperata.a fel* l !amang refwel-p "- Alagement N.s te a e ans an of rument t. tetMasta; ma nwa. Creund & resset.aea test of NT reehascal detectors and cablee manat .r

3. ISf m'4' ate ts ue Alast-nent NT *eceanacal f

,'f' ma n.a 4 y, Cea.yvesataan test depers! A reena aare test et N: tec ke.st al g eeseet.. a.4 c. :,. ma n. a: ti ] 'I g*. - B-19 Babcock WIcox f

~~- ~ Table 1300 2. Regiaired Inspections Proc edure Sve t em / c omponent ine o-etion tererence 7' req uene, 1. Reactor vessel In service inspectise IM4 01 Reactor coetant pump Seal ins pecume Annually or as 2. andseated try es. persence e 1302. Plant Calibration Procedures 1302 01. Reactor coolant system heat balance (primary) BLW. 1302 02. Nuclear steam supply system heat BLW L balance (secondary) Customer 1302 03. Calibration of source range nuclear instrument by neutron check BLW source 1303. Instrumentation Calibration Procedures 1303 01. Nuclear instrumentation and safety BLW system 1303 02. Integrated control s) stem B&W 1303 03 Reactor nonnuclear instrumentation B&W 4303 04. Rod control system BLW 1303 05. Radiation monitoring system Customer 1303 06. Auxi!Iary system instrumentation B &W & 3 Cus tome r 1304. Periodic Test and Inspection Procedures 1304 01. Reactor coolant system in-service ins pection 1304 02.. Post refueling physics tests B&W BLW 1304 03. Reactivity depletion versus burnup ~ 1304 04. CRD trip respcnse B&W 1304 05. Pressurizer relief valve (shop test) B&W Babcock & Wilcox 11-20 - =. 3, 2.0 u.c 4;9 g g 9: l w t - __ ___L j E. o... - -. -. -

?. j i I W; 1304 06. Reactor protection system trip response time BET i 1304 07. Reactor protection system trip i g logic response BiW 1304 08.* Reactor building leak rate test Customer E-~r v J u ) NV L.';j __y_ hU). q -*v. x. - l _ Ei J - - ~ - - - - - - - y*w n. i */ bi< D3 .k.\\ E] ['

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,a 1400. MAINTENANCE PROCEDURES Maintenance procedures include instructions for clean areas. layup of affected systems and components. and sequence of operations. Detailed removal. replacement. and disassembly instructions are found in the referenced vendor and component technical manuals. Each maintenance procedure contains the follow;ng sections: 1. Purpose s 2. I.imits and precautions 3. Initial conditions 4. Services and equipment required 5. Quality control ' required .g 6. Radiological' controls required 7. Procedure (sequential steps) 8. Final conditions 1401. Reactor Coolant System Maintenance 1401 01. Reactor coolant pumps B&W - - 'g 1401 02. Pressurizer relief valves B&W ~ B&W 1401 03. Steam generator Tube plugging Cleaning ~' 1401 04. B&W 1401 05. NDT sample removal 1401 06. Incore monitor removal and BLW repla cement l 1401 07. Pressurizer heater removal and BLW replac ement SLW l 1401 08. CRD removal and replacement Babcock & Wilcox B-22 3 _~ l ;L O 4-C 119 6 3 F 1 { { [' ~

~ 3, ~ .. 4 \\ l o F. ~ 1401 Co. SC relief valve terrioni and J.dB replacement Customer 1401 10 w.o 1401 11. Reactor internals. removal and replacement BLW l. 1401 12. Reactor ir.ternals vent valve removal { ;- and replacement BLW 1401 13. Reactor coolant temperature detector remon! and replacement BLW [.%f 1401 14. Pressure and differential pressure f* detector removal and replacement BLW Q, 1401 15. Use of freeze seals Customer y.s 1402. Auxilia ry Svstem Maintenany 1402 01. HP injection id purification { filter replacement B&W ry: Q3 1403. Instrumentation and Control System Maintenance , y. ~ ~ 1403 01. Nuclear detector removal and replacement (includes electrical 4 checkout) SLW b y. b)

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~. (2 1404. Steam System Maintenance Customer f_. - A, f,,=, b] .M., 1405. ElectricaTSystem Maintenance Customer ,r.... f.. a I B-23 Babcock & Wilcox l a.o ys is s t s

s 1500. RETUELING PROCEDURES f I The reactor is refueled approximatel,y once each year. At that time, as dictated by the fuel management schedule, about one-third of the core fuel elements are rernoved, the remainder are rearranged, and new elements a re laserted. The refueling procedure includes those operations unique to refueling. They do not duplicate such operations as cooldown and reactor building purging, which are found in the plant operatinit procedures. These procedures are arranged is normal se. quence except for those that can be performed independently of the main refueling sequence. Operating procedures for fuel handling equipment are found in the technical manuals for fuel handling equipment. Equipment opera. tions be. yond the scope of the technical manuals are included herein. 1501. Limiis and Precautions B&W 1502. Refueline Operatic,s. Sequence of Events B&W 1503. Preparation for Refueling B&W Equipment Building.and services New fuel trar.sfer and inspection Seal plate installation inst rumentation s 1504. Closure Head Removal and Replacement D&W Electrical L fluid system connection & disconnection Control rod latching L unlatching Stud removal and replacement Head removal and replacement Head seal leak test 1505. Reactor laternals Removal and Replacement BLW S&W 1506. Tuel Handling Babcock & Men _' B-24 = a.o yg hvo in v ..---r.. --n ~, .,_.-n, ..-,v. ..--.--.-~r-,, ,,v

I, .f. w. I 1507 Inco're.'.fonitor Handling During Refueling BLW 1508. Failed Fuel Detection and Hand!!ng B&W Q. 1509. Neutron Source Handling B&W -9 1510. Spent Fue1 Shipment B&W k' :.. - = _w I Dr.: ~- V, j b:-Q _v. _M% E-1 ~ sps. Q ~ _cjf v Ce f,5 A. ~ ' ' .eN E-~1

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.v.~,.-..--. .-. m.,..e.,. ~:.-.-....... .v.....-- ~. S: g. g ,J 0 J a. ~ 1600. RADIOLOGICAL CONTROLS Customer 1601. Limits and Precautions 1602. Monitoring Procedures 1603. Radiation Monitoring System Set points System operating procedures System calibration procedures 1604. Deconta mination Personnel decontamination Equipment decontamination Area decontamination ,g l 3-26 Sabcock & Wilcox ) mOLLC [t.

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3 llin N.. EQ v EUJ -V_ E.23 _ R t* i APPEND!X C p-AIC *.e::er Concerning Cor.versica cf Pru.stor.a1 to Pern anen: License i 5_.._3 ey. y;

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La /*. 1 L3 I A 1 y> ./ gH .s. s l { C-1 Babcock a Wilcox l 5 ' O u.c. }'.o e 3 6,' ~ l 4

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i TAC 1!.1TY 1.! CENSING ACTIONS (Trom AEC Public Document Room) i.etters similar to that below are being sent out by the Division of Reactor I.icensing in connection with conversion of provisional operating licenses to a full-term licenset 'in anticipation of the time when you wil! be ready to convert your provisional !! cense to a full-term license, we offer the fo!!owing guidance and comments fer your consideration in preparing an app!! cation for such a license: "1. The ap;,!! cation should provide dets!!ed consideration of the facility operating history, including confirmation of design bases and objectives. the signifleance of any plant problems that may have oc-curred and the remedial actions taken. In addition, it should support the adequacy of the performance and competence of the licensee's orga-nization during the Provisional Operating 1.icense period, including on- ~~ ~-~~ ~ ite staff, technica'! support groups and advisory committees. Fu rthe r, s it should discuss sigr.ificant changes that have been made to the facility t [ 1 since the Tinal Safety Analysis Report was prepared; however, extensive detail is generally not required regarding design and analysis of changes .that already have been submitted to the Commission for approval. Com-ments and recommendations cor.tsined in pa st letters of the Addsory Committee on Reactor Safegua rds concerning Unit No. I should be con-sidered in your application. N 5- ' '. The application should include an analysis of Unit No.1 1 in considerat.on of the criteria now being usec by the Commis sion in evaluating e.ew application.s for nuclear pow *er plants. Specifically, t your analysis should compa re Unit No. I with the General Design Cri-terta for Nuclear Power Plant Construction Permits published as a' pro- - posed amer.dment to 10 CTR Part 5,0 in the Federa! Register on July !!. Sabcod Nm C +1 i k

. ~ - - e ,.I 3.- e. [ s i.,. ,,, j,..,. .lM 1967 ard with the Proposed IEEE Standard for Nuclear Power Plant Protection Systems. e !;2c,L j "3. We have specific interest in the topics listed on the 9.o. enclosure. Accordingly, your analysis should consider each of these topics to the extent app!! cable to your facility. For those topics not n

w.-~s Y

adequately considered under items I and 2 above, your anslysis should discuss the adequacy of the facility with respect to each topic and indi-g cate what reasonably could be done to approach more nearly current design criteria and to improve overall operational safety. iii M-p "4. It is also requested that you include with your applica. tion proposed technical specifications, including bases, in the new form as set forth in the proposed amendment to 10 CTR Part 50 published in the Federal Registe r' on August 16. 1966* * * "In order for the staff to complete its evaluation of your applica-tion. Information is required on the,fo!!owing specific subjectst "1. Your plans and schedules for periodic inspections of g M the primary system and of containment; t3 g "2. The methods by which you detect and cope with reac-tivity and power distribution anomalies; K "3. Your methods and criteria for determining excessive primary system leakage and procedures regarding response to detected. and suspected leakaget WI "4. Your program for insuring the adequacy of the safety b,g, system with regard to current design and performance criteria, and the A*- justification for any deviations therefrom; If your. control and, safety sys,tems share components g Pf- *- ' or subsystems, a detailed review of functional, preoperational and in-service tests performed to provide assurance that this situation is ac-ah p9 ceptable. Including the bases for selection of the faults assumed for b purposes of analysis; tk pp 3 "6. Your program for materials surveillance for the pres-sure vessel: N }.p.. 9 a%, A Babcock & Wilcox F' 4 C-3 i, [p.0u,-C. ' : o. s 3 a. ' [_ E

.s ..-~-.------....--........4,, l f. i "7. A description of'on-site and off-site emergency radia-tion instrurnentation and of ;.roposed emercenev stoced'ures for imple-mentation during and followi.sg an accident: "S. Methods for providing independent review of ' proposed . changes to procedures, plant modifications. and audit of p! ant operations;

  • "9.

A description of procedures and equipment for fire protection and fire prevention: "10. Provisions for monitoring discharge of radioactivity to the environment and for limiting such discharges to acceptable levels: "11. An analysis of the effects of the loss of off site power and a de'scription of provisions for emergency power: "12. A description of operating cond:tions requiring adher-ence to detailed written procedures includine. as a minimum. sta'rtup. normal and abnormal operation. and shutdown of the plant and major systems, abnormal and emergency conditions. refueline. and mainte-nance operations which could affect the safety of the olantt "13. A description of the minimum acceptabic functional operating organization and provisions for prevention of degradation of staff competence over the service life of the facility; and "14. Identification of items that require further analy_ sis. testing and/or review subsequent to the licensing &# tion." l l Babcock & Wilcox g 2.0 4.-C. Q@5? r L {

I . ~ ~.. .... -. ~ ~.. - - -. - - - - .~.;, n. e I 4 .f..'*., ~ V,- i EE bu w [i.'.Q w< UV -<.f APPENDIX D Startup From Cold Conditions [ _.:,.-3 l N-i g;.g _..3 =. E- -, -g r $6 l l .~ t.-,s\\ . = _ /.,Is, V L

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.~ 7,, ). ..I a t N i i ) 1 1102-02. STARTt*P TROM COI.D CONDITIONS a 02.1. Purpose The procedure defines the major steps involved in taking the re-actor plant from a cold condition to a hot critical condition at 15% power. I The procedure assumes a startup following refueling. Reactor coolant pumps are the source of heat for the heatup. An auxiliary source of steam is required. 02.2. I. imitations 02.2. 1. The maximum heating and cooling rate of the reactor coolant system, including the steam generators, is 100 T/hr. The op-eratct will observe reactor coolant system average temperature read- ~ angs for loops A and B on the console and carry out nece'ssary actions to prevent excessive heating or cooling rates. 52.2.2. At reactor inlet loop A and 3 temperatures less than 450 T. iia more than three primary pumps may be operated. This is to ] prevent core.lif:Ing due to pressure difference across the core. 02.2.3. During 'heatup the temperature differential based on average tube temperature and average she!! temperature shall not ex-cred 40 T. This as determined from primary system temperature loops A and B iodication on 'the consoir and computer and from readout of thermocouples (SS2-TE-I through 5) located on the shelt of each steam generator. Shell temperature data are inputs to the plant computer. s. 02.2.4.\\'A* hen the reactor is operating in the range between 0 to 158*. power, reactar,, produced steam may be used for turbine warm-sng. rolling, and' avnchronization. Any steam used for auxiliary func-tions bslow the no load temperature will reduce the heat:ng rate. 02.2.5. P.eactor' system pressure shall not exceed 500 psig until the reactor syst m temperature is equal to the nil-ductility B bcock & Wilcox D-Z I 2

s' .......q 3 ,o . {. 3. a [ "N.] temperature plus 63 F. Charts are to be prodded to the operator which show updated pressure temperature !!mitations. ..e 02.3. Plant Heatup Procedures 02.3.1. Initial conditions are assumed to be as followst g.{ l. Head installed and gas'hets leak-tested. j 2. Reactor coolant water level 6 inches below {," ',I-] fla nge. s 3. Reactor temperature =100 F. 4. Na blanket in loop high points. M. 5. Incore instrementation. installed. ((

6. Steam generator secondary side water level

=30 feet with Na blanket. 7. Decay heat system in operation. 02,3.2. Open vent lines as followst 4 -[] 1. At top of intet piping bend to steam gen-erators (two vents on 36 inch pipe). y-2. Center control rod drive housing. 3. Incore monitor tubes at pressure flange. k 4. RC pump vents. s R, - 02.3.3. Check out all instrumentation; fill vent or drain lines Y and elements as re,alred. Conduct precratical check of safeguards in. s t rdmenta tion. Actuate ECCS bypasses as necessary. Conduct N1 f-{s! source check. ppm H BCs in borate stor-l 02.3.4. Establish that there are 3 . 4 age tank for initial filling. On subsequent fill. establish that concentra-tion in bleed holdup tank is ppm. This verifiestion is obtained from 8 gg a sample analysis. 02.3.5. Line up high pressure injection system from letdown d stora ge tank to injection lines on CR D ses!s and pump seals. Line up { reactor coolant system bleed transfer pump to letdown storage tank. !.ine up sustion of RC bleed transfer pump to appropriate bleed holdup tank. l t 02.3.6. I.ine up feedwater cleanup system. f..w p,a, sabeeck micox g7 a.3 .l' ~ 6--xA-Rm a.O u-g 00 6 4_2 g

y = ;.... ~ 7- / 02.3.7. Start RC bleed. transfer pump and establish maximum level in letdown storage tank. 1.Ine up blee'd transfer pump via bypass around makeup pumps. 02.3.8 Start bleed transfer pump

  • to start filling reactor coolant system and to apply seal water to CRD seats and pump seals.

Close RC pump, vents when water runs out. ' 02.3.9. Start auxiliary boiler or line up auxiliary steam supply and !!ne up to startup steam header. ~ 02.3.10. Start condenser cooling water flow. 02.3.11. 1.ine up steam supply,to steam seat regulator and establish turbine seals with turbine on turning gear. 02.3.12. Start hot well or boo' ster feed pump (s) and establis,h 25.** flow through the feedwater cleanup circuit. During cleanup of feed train, establish startup steam,at about psig to'shell of feed ~ heaters and/$r to maintain feedwater outlet temperature at about 200 F. 02.3.13. Start condenser air ejectors' and/or vacuum pump. Establish approximately 26 inches Hg vacuum in condenser. 02.3.14. %' hen feedwater reaches acceptable quality, open see .y ondary vent !!nes on each steam generator, and fi!! steam generators to" ~' . 30-foot level indication by opening startup valve to each steam generator. (Condensate booster and/or hot well pump (s) running.) Close vent when sta rtup level is obtained. (This step wt!! not b'e required if initial con-dition 6 is met: if required. observe OTSC temperature limits.) 02.3.15. Open turbine bypass valves to obtain condenser vacuum above water level in steam generators. (This step is not required if re-actor average system inlet loops temperatures as read on RC5-TR on

  • Do not use makeup pump to fill reactor coolant system since its shut-off head is above nil-ductility limits on reactor coolant system pres-

~ sure. 200 F . 25. flow is based on a minimum of Z (ps flow in the feed train. is based on converting hydrated oxides of iron to magnetite and deaera- .D tion of feedwate r.

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Babcock &Wilcox D-4

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e. [f - 3 y> __h O a!! four 25 lach loops i*s above 220 F with decay heat system flow, if -? steam generator dowmcomer temperature is above 220 F. and if the ~ mass weighted average OTSC shell temperature is not more than 40 F y. less than reactor coolant temperature.). r0 !;. 02.3.16. Close reactor coolant system vents that were opened In step 3.2 mhen system fills and s3ter issues

  • from vents on 36 inch 4

gr. ~] pipe. Till until pressuriser level is feet or pressure is 50 psi. Vent each CRD housing and instrument connections. 02.3.17.' Energize all pressurizer heaters (manual) and estab- { ',. ' lish 135 psig pressure (RC3-PR2) for NPSH on RC pumps. (This re-s. },' quires about 2 1/2 hours from 70 T.) Periodically vent pressurizer at 15 minute intervals,to purge nitrogen and other noncondensibles. 01.3.18. Start cooling water systems required for reactor cool-g. Conduct cold preoperational physics tests and CRD ant pump operation. p Bump RC pumps and vent lines at top of 36 inch pipe. (Ob-line tests. y,.f serve @CP start-restart limits.) 02.3.19. Sta rt, in sequence, three reactor coolant pumps when

p. r.,j psig pressure (RC3 PR2) is obtained and required services (cool.

Ing water, etc.) are in operation. E _d 02.3.20 Stop and isolate the decay heat removat system. {=_ .Yr 02.3.21. Sample and establish RC system chemistry, including {.,:.j H addition to letdown stora ge tank. t ... Check RC system temperature pressure ND T chart 02.3.22. }[ to establash maximum pres sure, and hold pressure above minimum {] NPSH and below NDT limit until RC system temperature is above NDTT + Start raising pressure to normal ope rating pres sure (2200 psig) ~ 60 F. T' by placing heaters in automatic cont rol (to insure cutoff at 2200 psic). .ds l ~ l L " Visible w ter flow out atmospheric vents or visible through sight ports A of vent lines. {., r t.finimum NPSH for RCP's. 1 saecock s wiicea 3., m g l j j

l '. '. ~ J ,~7s' l ~ s. l 02.3.23. When reactor coolant system pressure reaches 800 psig or 350 F (RC3-PK2) start sea! water flow and ' cooling water Gow I ] to reactor coolant pumps. 1.ine up core flooding tanks. 02.3.24. When steam generator temperature reaches 220 T. close all turbine bypass valves Set bypass valves to open at 400 psig 4 and transfer bypass valves to automatic. 02.3.25. When pressuriser pressure reaches Z200 psig. place pressuriser spray valve on automatic pressure control. Maintain pres-surizer level at minimum by adjusting letdown flow (manually by HP3-MIC) and the makeup dow by placing pressurizer level controller (RCI-i !!C) setpoint at least I foot above pressuriser heaters. When steam generator ' ressure (SS6-PI) reaches 400 02.3.26. p psig, line up and start one' boiler feed pump set to ininimum speed and place startup feedwater valves on automatic in the ICS system. 02'.3.27. Open turbine warming valves and drains. P re s s u riz e turbine with auxiliary steam for w2rming. 02.3.28. When reactor coo! ant system reaches 450 T start fourth reactor coolant pump. 02.3.29. When reactor coolant system reaches temperature above $32 T, turbine bypass system will pass steam to condenser to ~ maintain reactor coolant temperature... Steam produced may also be used for feed train h'ea't'ing arad tu'!bine wa rming. Establish normal pressurizer H;O level and set letdown flow at > ' gpm. 02.3.30. Conduct hot precritical testing including CRD testing. ~ 02.3.31. Check nuclear instrumentation for proper functioning, l 02.3.32. Take reactor crttical as follows: I l N. 1. 1 sing known values of core lifetime, fuel load-t l tag, tsme, s hutdown, and tempe,rature; pre-dact erstacal rod position and regbired boron concentration. " Select letdown flow to permit heatap from 5 32 F to 570 F at 0.5"v' minute without further adjustmer.t of 1.3 flow. Sabcock Ncox D-6 a. O L'- C \\. 9 i & 5 8 v i i

+- .~ r s e 0-l- %E] .. ] ..'g 2. %"ithdraw. rod groups 1 - 4. 3. Deborate to precalculated concentration. hs 4. %'ithdraw rod group 5 until criticality is

g. d achieved.

l 5. If not critical on group 5. Insert this group and deborate an additional ppm. Caution: Make certain that all rods of grou'ps 1 - 5 are operable. r'. 6. %*ithdraw rod group 5 for criticality. -Y] Cautiont !! reactor is not critical return a!! rods to bottom and determine why pre-dicted values fail to cause criticality. b,,4 02.'3.33. At this point, reactor control is on hand at rod drive 3 - 2 f pa rt of console. All selector stations in integrated control system should Es,] be on hand except for startup valves in feed train, and turbine bypass valves. Check and/or set all limits in ICS. e p.q d 02.3.34. 1. S*ea r end of turbine warming period, bring reactor to 10% and about 565 F. Transfer the reactor control to ICS by placing CRD system on auto. 2. Bring turbine to speed. L4 g

3. Synchronize and initial load the turbine to mini-g mum block load established by turbine manufacture normally between L..4,J, 5 - 8% load.

l .C, - 4. Hold initial turbine load for 30 minutes (turbine minimum wa rmup period). ?fm]'. 5. Raise turbine generator power to 10';, in hand, at a maximum rate not to exceed the temperature limits established by turbine manufacturer. { 02.3.35. Raise reactor and steam generator load to 15%. I.ine i {M' up and load second feed pump. place both main feed pumps on automatic control at ICS to hold at minimum speed. f ine up emergency feed pump. place on auto s ta rting. (Second feed pump may be delayed if not required E~ 2 for load capability.) d sta f.. :,, 02.3.36. Place main feedsater valves on automatic control. L I h.a.m -.a e i d [ )., !c3x D-7 Sabcock & Wilcox I _. 1 .a.0 4-c 19 6 4 e 1 E

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02. 3.31.

1. Dalance steam generator load ratio in feedwater controls and place steam generator control station on auto. 2. Balance reactor coolant temperature set point at 'l 579 F. Inne up steam generator-reactor control station and transfer re-actor controls in ICS to auto. 3. Dalance feedwater contro,ls to reactor and transfer feedwater demand control station,to automatic. All stations in nuclear steam supply system are on auto and load is established by steam gen-erator-reactor control station. 4. Transfer steam generator reactor control station to auto. The NSS will hold a minimum 15".' load which is a preset mini-mum level in the ICS. 02.3.38. Check dispatch system (Dispatch Frequency Contro ) i fo'r operability. Check that all track /runbacks are clear. 02.3.39. Set load demand to 10',at unit. load control statidn and plfde turbine control on auto. (This transfers turbine from Electro-Hydraulic control to ICS.) Plant control is now on hand from unit load control station. 02*. 3.40. Increase load demand from to to 15".. bring the turbine up to NSS Ic,ad. As turbine consu'mes steam the bypass system wi!! close 5 to control the urbine header pressure at 900 psia. 02.3.41. At ;15". load', the plant is ready for power operation, either manual by the operator or a ito from the Dispatch Frequency Con-j trol. 02.3.42. Set load and rate limits for plant in ICS for specified power range response. 02.3.43. Concurrent with po'wer operation at least one day prior to scheduled shutdown, degas reactor coolant system by stopping addi. tion of Ha at LD tank, and periodically venting accumulated H: and other gases to WD system. Babcock f.Wilcox D-8 I I l

s. l .{. _ a. { .~ .x .r., i i.. p-e. i , y. h*f m s 1 --w m en a +-- -J 7 APPENDIX E p-T!!!!ng and Draining Fuel Transfer Canal h ...... _k\\ L_.J _.f.(.% _ LJ yj .s. 4 M *M I .~. N 4 %

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e .--. -.- - ;~. ~.. t f g 1 !!02-15. TILLING AND DRAINING THE FUEL TRANSFER CANAL ! $.1. Fi!!!ng 15.1.1. Initial Conditions 1. RC system ready for fill to refueling level, reactor vessel head removed. RV water level below flange. 1 2. Seal plates installed between RV flange and fue! transfer canal floor. 3. Barated water storage tank.S!!ed with reactor-grade wa te r. 4. T!anges removed from canal end of fuel transfer tubes. 5.~ Refueling canal cleaned and ready for fill. 15.1.2. Pre-Sta rt Checks 1. Decay heat remont system operational. . L L ~._... _._. 2. ~ Core flooding system 14 inch isolation valves shut. 3. Spent fuel cooling system operational. Soric acid concentration in SWST r ppm. .l. 5. High pressure injection system operational. s l 6. Dleed holdup tank full of reactor grade water, borated N to y r,p horic acid, and bleed transfer pump (s) operational. 7. Waste disposal system vents and drains operational. I l 8. CRD seal water injection lines in RV head a rea blanked, or associated valves shut. 9 Fuel transfer canal drain to RV cavity blanked. \\ ,./ i E-2 Babcock & Wilcox % o u.c, @. 6 4 s.. l i t i c t i, s

~ s 'r j }. __,l l i F.}-] 15.1. 3. Operation ~~ I. ! ine up from bleed holdup ' tank and bleed transfer .i pump. through the letdown filters, to the HP Injection piping an'd reactor coolant pump seat injection piping. 0 y h*2.e e: Seal uter must be injected to reactor t _v' coolant pump seals during canal fill to .. J.3 prevent particulates in reactor coolant lJ system from entering pump seats. Seal water injection must continue until the ' fuel transfer canal is filled. h... 2. Open high point vents in pressuriser and steam gen-erators (primary side) to provide a !cak-off path for the purge gas in "7 these components.

3.. Start the bleed transfer pump (s) to fill the reactor vessel through normal makeup injection and reactor coolant pump seal Injection lines.

4. I.ine up the sper.t fuel cooling pump (s) from the borated water storage tank to the fuel transfe r canal vsa ulves IST-V9 and IST-V10. -4 5. When the water level in the reactor vessel reaches E. .] the reactor vessel flange, start the spent fuel cooling pump (s) to fill the - 2 = fuel transfer canal. b .When the canal is filled to the desired level. stop 6. the spent fuel cooling and bleed transfer pumps. n. Restore refueling valve lineup. 7. 15.' l. 4. Final Conditions [* Reactor coolant system fi!!cd to refueling level with b -) water of proper purity and boric acid concentration. A ~ 2. Tuct transfer canal filled with water centaining re-fueling concentration of boric acid. ~4~./k 3. Decay heat remon! system in operation as required. 4. Spent fuel cooling system in operation as required. .A e.1.. E. .D g SabCCCk & WilCCE g,3 I r -- ,a.C U-C. l9@50; i i

e ..., c,;.. 8,' ,a s ~ \\ ~.1 c .o 15.2. Draining 15.2.1. Initial Conditions 1. Tuel handling operations complete. 2. Reactor coolant system and fuel transfer canal filled to ref.seling level with water of ppm concentration boric acid. 3. Borated water storage tank ready to receive gallons of contaminated water. Refucting equipment and instrumer.tation removed 4. from canal and bagged. or suspended around canal for spray decontami-nation during draining operation. 15.2.2. P re-Sta rt Checks ~. J 1. Decay heat removal system operational. 2. Spent fuel co' ling system ope rational. Component drain system operational. 3. Regulated nitrogen supply available to pressurizer 4. and steam generator primary-side vents. Demineralized water available in canal area (for 5 washing down canal and equipEe'ntluring drainir.g operation).

6. Constant air monitoring equipment operatienal.

d 15.2. 3. Operation 1. Close the stop valves in the fuel transfer tubes. Line.up the spent fuel cooling pump (s) to take suction 2. IST.VIO. and IS F-on the fuel transfer car.a!, through valves IST-VO. V11. and deliver to the borated water storage tank. 3. Start nitrogen purse of pressurt=er and steam gen-e rator primary side. Caution: During the canal draining operation it is importar.t that the pressurizer and steam generators be maintained at or j near R3 pressure. A very small posi-tive pressure in these c'omponents at Sabcock & Wilcox g.4 1 e _q - a.0 4.-C "i.0 6 5 1-i k

....,s. = p the e d of the draining cycle could re-sult in loss of decay heat removal espa-hslity upon equalization of pressure with RS atmosphere. N' - 4. Start the spent fuel cooling pump (s) and draln the refueling canal. Interrupt draining at approiimately 10-foot intervals j i and determine true water level by venting pressurizer and steam gen-e rato rs. 5, When the borated water storage tank is filled, or before the deep end of the canal is completely drained, stop the spent 1 fuel cooling pumps. Drain the remainder of the water to the reactor building normal sump through valves ISF-V7. and ISF-V3. Commence e' recirculation of BWST through SF system purification loop. s 6. During the draining operation, wash down the canal [ walls, refueling equipment, and canal floor using demaneralized water and working toward the deep end of the canal. Drain this water to the RB normal sump. Not et Continuous washdown of the canal and ' jl equipment during draining operation is k not required. however, washing intervals must be timed so that the canal and equip-ment are not allowed to dry before they a re w2shed the first time. .g ~' ~# 7 When the canal water !c' vel is reducrd to RV flange ,g level. lower the reactor vessel water level to 6 inches below the flange by opening a primary coolant loop drain and pumping to waste disposal through the component drain pump. Accurate determination of water level before ansi after this operation is particula rly important. S. Secure the spent fuel cooling, compo..cr.t drain waste disposal, and nitrogen purge systems and the RS normal samp. -ai i o. Install blank flanges on fuel t ransfer tubes. ..g ....a

10. Complete cleanup and decontamination of fuel trans-fer canal, refueltag equipment and RV flange area. Remove seal plates p,

f rom RV annulus. s.

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.......C....___ ,,.......Z.' ~ c ..~._'_:___'. T i. 15.2.4. Final Conditions 1. Tuel transfer canal drained, clean. 2. RV water level 6 inches below flan 5*. i 3. Decay heat system in operation as required. Spent fuel cooling system in cperation as required. 4. 5. Borated water storage tank full. 6. Recirculation of BWST water through spent fuel k cooling system purification loop in progress as required. 7. Void space in pressurizer and steam generators blanketed with nitrogen. Decontamination and storage of refueling equipment 8. in progress. 15.3. Infrequent Operations ~ 1,. .15.3.1. Adjustine Water Level

1. 'w*ater level is adjusted using the inst' ructions of paragraphs 15. I and 15.2 as applicable.

~ 15.3.2. Cleanup / Purification'of Canal and SF Pool Water 1. Instructions are included in Spent Tuel Coollag Sys. tem Ope rating Procedure. J i .g i .I Sabccck & Wilcox E-6 l L 2.O 4-C p.o 6}s k

,s-,q, g _L I R.jd ((5:. y Wg Y E4 .,a ~ L.Q E13 4 APPENDIX T Core Flooding System Operating Procedure c,. 5 9 g-Q u- .4 LG .A.. t g-;_3 ~ _A _ b b3 d' 09 A-T;D Baecock & Wilecx = ( _]. i i ~ u 5 4_.' 3 ^: UF 06 %L,c

,[ . f., * - ? .c ~ _g t i 1 I t104-01. CORE FLOODING SYSTEM OPERATING PROCEDURE 01.1. Core Flooding (C T) Svstem Descriotion This engineered safegua rd system provides 'a volume of borated j water, under nitrogen pressure, for injection into the reactor coolant system in the event that reactor coolant pressure in inadvertently re-duced to less than 600 psig during operation. It is a passive system because no operator action is required to effect this injection. The C F-system may be isolated from the reactor coolant system during reactor [ j shutdown, and must be isolated from the reactor coolant system any time the reactor coolant pressure is intentionally reduced below 650 ~ j psig. CT system pressure is maintained at psig, maximum, when reactor coolant temperature is below (NDTT +60) F. ~ System parameters a ret . i Or.e ra tional ~... Design Maximum Nominal Minimum =, ' 600 585 Pressure, psig 700 615 Temperature. F* 300 120 104 75 ~ Le. vel, it *

  • 14 12 11.5 11 1

H B03 concen-13.000 20.000 13.000 13.000 i l tration. ppm l l 'No temperature-senstag instrumentation is installed on CF ta nk s. Use reactor buildanc ambient temperature. 88 Level instrumentation is of the dry-reference-leg type. Any I l

  • time that the level reading ts suspect, the reference-leg trap should be dratned to assure that water in the reference leg is not causing a false level sadication.

l Babcock J. Wilcox y.2 l l 4 W a.O u-c [ o g s i l i 8 v l i

l -^' \\ .~.,- '..s ( s.. =. a. ) .] / \\ i 01.2. Normal Operation 01.2 1. Initial Conditions 1. CF tanks filled to 11.5 : 0.5 ft' with reactor grade water. borated to 13.000 ppm boric acid. 2. CF tanks pressurized to 600 : 15 psig with nitrogen. 3. CF tank level indicators on each tank ' agree within 3 inches. 4. 'CF valves CF-VI A and CF-VIB shut. 4 5. C F tank vent. drain, fill. and sample valves shut. 6. Re.netor coolant pressure 650 : 10, psia. increasing. y 01.2. 2. Starting l. With reactor coolant pressure at 650 : 10 psig, in-(,d creasing, open valves CF-VIA and CF-VlB. 2. Monitor CF tank level and pressure. An abrupt in-crease when the tank valves are opened is an indication that the CF 14 inch check valves are leaking, and shall be cause for shutting valves {] CF' VIA and CF-VIB for corrective action. ~ ~ 3. The,JF system has no active function 'during reactor -

b.,, -

plant operation. Therefore. the fo!!cwing evolutions involvang the CF Af. a, system are performed only to maintain required CF system status. M 01.2. 3. Securine 1. Shut valves CF-VIA an'd C F-VIB. when reactor cool-L :1 4 ant pressure is 650 : 10 psig, decreastng. during plant cooldown and ps depres s u riza tien. W Notet Isolation of a CF tank durini: plant opera-3 .f* tson may be re<1uired due to a malfunction an the CF system. " Reactor Plant Op-erating Procedures contains instructions for plant operation with reduced CF sys-y tem protection. e .A~~A. I_, Babcock Wilcox Wilcox F.3 1 10 4-C @ s 5 4 ~ g { c .-._,-_m, y

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.a 4 i W e 2. Open quench tank vent valve and reduce CF tank pressure to psig by alternately opening valves CF-V3A and CF-V33. venting to the quench tank. Close quench tank vent and valves CF-V3A and CF-V3B. ~. 01.3. Initial. Fill

01. 3.1. Initial Conditions 1.

The CF system has been cleaned to the requirements of reactor coolant system cleanliness. 2. Valves CF-VI A and CF-VIB a re shut. 3. Reactor grade water available to CT system through high pressure injection fill line. W 4. Borated reactor grade water available to CT system from chemical addition or waste disposal systems. Borsted water is normally available as follows: Source of boric acid must be sampled prior to fill for determir.arion of actual concentration. 5 a. Boric acid mix tank (CA system) - up to 7 weight percent concentrated boric acid. b. Concentrated boric acid storage tank (WD ' system) - 5 weight percent boric acid. c. Miscellaneous waste holdup tank (%'D sys-tem) - el.3 weight percent boric acid. ~ -~ ~ ~ ~ ~ 5. CF and associated systems operational. ~

01. 3 2. Sta rting Two methods are available to fill the CF tar.hs with un-

~ borated. reactor grade water: 1. B!ced transfer pump. from bleed ho! dup tank, de-borated water through fil! lin~e on HP pump outlet pipir.g. 2. HP pump (s), from bleed holdup ta.k deborated wa te r. 2 A flow restrictor in the tank fill line limits fill rate to 100 gpm. a t I Sabcock & Wilcox 74 ,--w-p ! ;L O 4 - C.4 i;0 6 5 M l ( I ki

.e 3, u 1. Line up the CF tanks to receive unborated water %d. using method 1 or 2 above. Line up source of boric acid to CF tanks. Open tank vent valves CF-V3A and CF V38. Cau'lon: First, open quench tank vent. 2. Till the tanks according to the following tabulation. Relative volumes are determined by the source cf boric acid selected and are calculated te res' ult ici 13.000 ppm boric acid in the CF tanks. v wt ", H B 03 Unbora ted 3 K source water,it Boric acid, ft3 8 1.3 0 (0' ind) + 940 (11.5 ') T 5 695 (8'-6" ind) 245 (3*) + 7 765 (9'-4-1/4"ind) + 175 (2 '-I-3/4") g.]

01. 3. 3. Securing h

I. Shur CF tank fill and vent valves. Secure fill pumps. 2. Restore normal lineup on systems used for fill (HP. +- CA and/or %~D).

3., Sample CF tank contents and adjust water chemistry per section 01.7, if required.

01.4. Ventinz (Depressurization) 5.y 7.

01. 4.1. Initial Conditions

.sk 1. C F tanks at greate r than requ' ired pres sure. s 3

01. 4. 2. Sta rtin g

? ?. 'Q e,. 1. Open quench tank vent. Open nives CF' V3A and ( CF-V18. allowing CF tanks to vent to the quench tank until pressure is i .stS.-. rguced to required value. --.d

01. 4. 3. Securing b.

1. Shut valves CF-V3A and CF-V3B. A. a 2 E' Sabcock & Wilcox F-5 .j .. - - ~ e -m_

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01. 5.1. Initial Conditions i

1. CT tanks at less than required pressure.

2. Nitrogen available to CT tar.ks (approximately SCT at 600 = 15 psig per tank for ir.itaal cha rge).

~ l 3. CT system may be in norms! operatton (valves CT-VIA and CT-VIB open. RC pressure >650 psig) or preparations under-way for plant operation (valves CT-VIA and CT-VIS shut).

01. 5. 2. Sta rtina

.l. Open r.itrogen fill valve. Observe tank pressure change.

01. 5. 3. Securing 1.

Shut' nitrogen (111 valve when CT tank pressure reaches 600 : 15 psig. 01.6. Draining

01. 6.1. Initial Conditions e.

1. Reduction of CT tank water level required'.-- Note: This procedure applies to adjusting CT tank water level (bleed) or complete draining, and may be accomplished with the CT sys-tem in operating or standby status. C7 tank pressure of at least 100 psig is recom-mended for draining operation. 2. %'D system ant!ab*e to receive required quantity of barated wate r.

01. 6. 2. Sta rtina 1.

Line up the %'D sy stem to receive water from CT ta nks. 2. Open valveis) CT-V2A and/or CT-V2B ar.d drain the C T tank (s). Continuously monitor CT tank level while drasning. e s Babcock & Wilco T-6 nQUrto65 ~. -

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01. 6. 3. Securing l

1. Shut valve (s) CF-V2A and/or CF-V2B when required ~.~ CT tank water level is reached. 2. Restore normal WD system lineup 01.7. Sa mpling The frequency and method of CT tank sampling and analysis are included in section of the Water Chemistry Manual. 01.8. Adjustine System Pa rameters y When it,is necessary to change CF tank Icvel, pressure or water chemistry. use applicable portions of sections 01. 3. 01. 4. 01. 5, and

01. 6 of this procedure. During plant operation, makeup water must be added through the hig,h pressure injection pu'mps (section 01. 3).

{ 01.9. Infrequent Operations 01.9.1. Hydrostatic Test {7. -i,] 1. Till the CT tanks solid with water, using the bleed 'a ' transfer pump and senting to the quench tank through valves CT-V3A and CT-V3B'. y' -- - ~~ t' 2. Initial and. if required, subsequent. hydrostatic tests ; will be conducted in accordance with TS/ / /201/t. .Pf 3. Following the hydrostatic test. drain the CT tanks to normal operating le0ct". admitting nitrogen to the tanks as the water level is reduced. Open the drain valve on the CF tank level indicator dry Icg and purge nitrogen through this piping until no water remains f.k, in effluent gas. ( OI.o.2. -Functional Test 1. A periodic CF system functional test will be per-formed in accordance with TS/ / /201.'2. at inte rvals spee fied in the Reactor Plant Operating Manual,

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