ML19344A902

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Forwards Response to Re Control of Heavy Loads Near Spent Fuel.Includes Fuel Movement & Core Alteration Procedures
ML19344A902
Person / Time
Site: Peach Bottom  Constellation icon.png
Issue date: 07/17/1978
From: Daltroff S
PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC
To: Stello V
Office of Nuclear Reactor Regulation
References
REF-GTECI-A-36, REF-GTECI-SF, TASK-A-36, TASK-OR NUDOCS 8008220571
Download: ML19344A902 (38)
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{{#Wiki_filter:- __ _ _ _ _ _ _ _ _. THIS DOCUMENT CONTAINS P00R QUAllTY PAGES PHILADELPHI A ELECTRIC COM PANY 2301 M ARKET STREET P.O. BOX 8699 PHILADELPHI A. PA.19101 SHIELDS L,. DALTROFF vect Passioth7 ELECTRIC PmCDUCTION July 17, 197'I Jocket o s. 50-277 50-272 'f r. '.' i c t o r Stello, Jr., Director Oivision of 3peratin; leactors Office of '*uclear Reactor F.e3ulation 'J n i t e d States Tuclear Regulatory Connission 'Ta s h in 3 t on, 7C 20553 near !r. Stello: Attached are our responses to your recuest for information dated '!ay 17, 1971, concernin? " Control of "eavy ': e a r Spent ?uel." If you have any questions or recuire Loads further infot.ation, pleasa do not hesitate to contact us. very t ru ly yours, .e

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50-277 and 51-271 'esconses to Peouest for Information Concarning Control of Meav" Loads " ear 27ent ?ual July I?73 '.ecuest _I Provide a diagran which illustrates the physical relatien istseen the reactor core, the fuel transfer canal, the spent fuel stora;e pool and the set lown, receiving or stora;e areas for any heavy loads-noved on the refueling floor. F.es,onse Attached are ?rint 7-11 for Unit 2 and ?rint I-32 for 'Init 3, which shou the lay-loan areas for the shield plu s 2nd reactor internals. Annotations indicate t 't e normal stcra;e areas for the inspection Sashets. F.e c u e s t _2 Provide a' list of all o'ajects that are required to be acted over the reactor core (during ref uelin;), or the spent fuel stora;e pool. ?or each object listed, provide its aaoroximate wei:ht and size, a diagran of th e novenent path utilized (includin7 carryin: height) and the frequency of novement. 7esconse -A. Over Teactor Core durinn ?.efuelinz The.follouin3 lists of o'a j e c t s contains only t'tose t't a t are moved over the core v' tile it is enposa. i u r i n -; refuelin; and maintenance. 'to s : of these OSjects aa-, se used anywhere in the upper portions of the reactor vessel. None of thea voul! travel over the sient fuel pool. Therefore, a dia3ran shoeing their path is not orovided. The c a r ry in 7 hei;ht of the objects couli Se sufficient to clear t 't e other objects on th? refuelin; floor. This vouli generally be no ;;r ea te r than ten feat aSove the refuelin;. floor lav21, an i 'would be as lov as is practicaSle. T': o s a. i t e ms that are largar than the diameter of tne reactor vessel, 173 : terefore cannot fall onto the cor e, are not a d d r e s s.a i. Ins,3ction ?latforn - This olitform, which vat:hs a p p r o nima t e ly si pounfs, sits on tha Circu When 19 2se. ?? its sh/sical nature, tcis ilitform shouli not 0 J

J o c h e't 277/50-273- ? ace 2 Control of leavy Loads 'Icar 3 pent ?uel fall onto the fuel because it vould be stopped by the shroud. In addition, four ooint ringin; is utilized which should prevent cochin; of platform iuria; novanent. The frequency of novin; the insoection platforn depends upon the outa3e schedule and the nature of the maintenance involved, but vould be in the range of'three to four~ installations and renovals par rafuelin?, outage. Insnaction Sasket, Lim 5twei~ht - This basket is used to lower a nan into the reactor to carform insoections an' 57 drolasing. It ve i;h s a p p r o xi ma t e ly 2,r93 counds. Uhen it is in use it is double ri 3;ed so that it cannet . fall onto the core. This double riggin; is establish 24 throu3h the usa of the refueling floor crana and a special vinch having an ener3ency pover source. 7 hen in use the lightveight basket can be positioned anywhere -around the perimeter of the reactor. Only one li;htweight basket exists USich is noveM betveen the units as needed. Insoection 3asket, leavvveicht - This basket is also used for inspection and hydrolasing, but, because of its additional shieliing, nay be brou;ht to within a f ew feet of the cora for control-rod-drive return line nozzle inspection and nay be used for longer stay tines. This b a s k e t-is double rigged in the sa e nanner as the lightweight basiet and nay be used anywhere a r ou n-i the perineter of the vessal. The so p r o ni na t e ly weight is 3,300 pounds. There is only one heavyuei.ht hashet shich is_noved betvean units as required. This cleaner wei-hs Undervater "acuu Cleaner approni ntaly 293 pounis and nay be ussi in the spen: fuel pool or the reactor vessel. Its use depends upon the anount of' debris fron operations. !ie cleaner is stored in the spent f uel pool and is b rouch t inte the reactor head aras under water. ~ Sun, Punos -_Juria; portions of the refuelinn outages suny pumps are used in the area surrounding the renctor vessel ~ flange. They are not used over the reactor vessel or core. They ranse in vei;ht fran f0 to i i pounds and are put in place each time vori is to be performed inside of the reactor 21:4 tTe water level losared. l Tia unsarvater "ndervater T.7. Ca era 2nd Small Tools c ane ra and small cools are use? in and around tu core durin3-naintenanca and refuelin;. The ca era sei;is - 1 1 eu '

Dochet-50-277/39-27S ? age 3 Control of "eavy Loads : ear Spent Fuel a p p r o.ti 7a t e ly tienty pounis. The sei;ht of tne small tools is ;enerally un er fifty pounds each. Fuel and Core Ce nonents - 20th new and spent fuel must be moved over-the core and spent fuel racks. A fuel bun.ile vet;hs a p p r o::i na t e ly 6 0 ", pounds. The possible damage that could Se done in a fuel Sundle drop accideat is assessed in Section 14.6.4 of the ?each 'otton Final Safety Analysis 'meport (? SAT). Tuel is noved in accordance with Tuel Mandlia; ?rocedure, '9-Se uhich is attached. Core components such as control rois and L3?.1s aust le noved over tae core. Th is is done in accordance viti yuel 3andlin; ?rocadure 7'4-l ? A and iystem ?rocedure 5.14.7, which are attached. Over Scent ?uel Pool As' indicated in laintenance Procedure 1.17.2, uhicN is attached, the crane in each reactor buildina has an interloch that prevents the la2ded hoo? from being move: into the area over the f uel pool. Y: hen a load s u c 'a as a spent fuel casi is to be noved into the c a s': area in the pool, the-interlock aust be bypassed by way of a tey suitch. 3yoassin; of the interloch is controlla? hy procedure. The following is a list of the objects that may be., o v e' d over the f uel pool ani 71tnin it. Shia71n; Cashs - M Q casy.,are coved into the casi area.of the pool. The casi area is the only portion of pool that cashs uay be carried over. "edun! ant ri;-in~ is used f or all casks. The lar;ast e s s ': is inches ir diameter and 204 inches lan; and uel;hs l'4,'C0 7cun?s. At present, use of casi is infrequ2nt, but this vill change shen a stora e or recrocessin; facility 's e c o 2s available. The frequency of usage vill depend on tha capacity of the cask used. These itens Soent Tuel Assemblies and Core Com7enents are also coved over spent fuel racks. They are addressed aSove in Section A to this rastonsa. "oiification _o_f t h e S,ent ?uel 3 tora e ?ool ? hila d tlp'tia Tla ct ric Company aas applici for per-ission to install high density spent fuel racks. Du rin ; the removal:of the ali racks 2nd installation of t 'i a ne i, racis'ani essociated.ecuipas,t uill iav: c 32 moved in and arouni tee. spent fuel. pool. ? roc 2Tures vill se established that will proaibit o v i a.. c': facts evar

~ Jochet' 50-277/50-273 Ta3e 4 ~ontrol of 'leavy Loads " ear, Spent Tuel 33 n3 for'the. installation 2nd racoval -active fuel. ?.1 1 of the racks'will-Se such as to nreclule the~dropain; of the racks.- (See 7.esponse-1) conttined in the letter dated '!ay I?, 1973'fron 2. J. 3radlay t o 0. Lear sad 2esponse 15 contained'in the' letter dated April 17.-1*?' fron C.J. 3:sdley to G. Lear.)- 7 ernest _3 'Jhat are the dimensions an/ vaights of the spent fuel ccats that are or vill.-Se used at your facility? .esconse 2he follo*iing table provides the requested i r. f o r ma t i o n for those licensed spent. fuel casks presently considered suitaSle for use at ?each lotton: Cask "oninal Mominal Soninal,Losded Desitnation 0.9.. In.* Len7th. In.*

  • ?eints,'Lbs.

SLI:1/2 47 197 47,590 'JLI 11/24 93 204 134,030 G: I?-300 54 20S 140,n?C 67. 1o_n_ 7o,, 3 " ?., - 4 .t o. 'r' .0,'o.n I J

  • xclusive of-Impact Limiting Jevices 7ecues; _i Identify _any heavy load or ensi drop analyses perferned to date for your facility..?rovide 2 copy of all s u c'1 analysas not oreviously suSnitted to the II?.C staff.

?.esconse Th-a possibility of a cash frop acciient - is addressal in t 'T e '?each lotton FSi2,~3upplement-1, questions 4.9.4 and 14.1 1 iro77ed fuel Sundle 2n a'ly s i s 15 contained in the ?each lotte? isal 3ection li.5.a. d kn. m ...m

J o ci e t' 30-~277/3?-27? Pa;e 5 Control of Eeavy Loads 'i e a r Spent Fuel 'equest.ji i Identify-any hetvy loads that are carried over equipment require for the: safe s hu tdo in of a olant that is ooeratin; at the time the load is noved. Identify what1 equipment could be.affecte! in the event of a heavy load h andling sccident (piping, cabling, pungs, etc.) and discuss t' e. f easibility of such an accident affectin; this equionent. 7escribe the basis for your conclusion. tes,onse Heavy. loads are not carried over unprotected ecuiptent required for safe shutdovn of the Peach lotto, Jnits. This is true when the reactor is operating and .s h e n it is not oneratin3 The physical plant of the Peach 3otton Units is such that the cranes do not pass over unprotected safety-related equipcent. leavy loads, by virtue of the crane locations, are carriad over reinforced concrete floors. If a situation vere to occur where a ieavy load iould have to be transported over safety-related equipment because no otSer path was available, the move vould be predicated by assurias that the safety'related equipment tr a s not required for safe shutdown at the tine of the nove. Recuest _6 i If heavy loads ara required to be carried over the spent fuel stors;e pool or fuel transfer canal at your facility, discuss the feasibility of a handling accident which could result in iater leah23e severe enough to uncover the scent fuel. 7escribe the basis for your conclusions. Resoonse 9eavy loads are prevented f rom being noved over the spent fuel pool and refuel slat by means of 2iainistrative controls 2ni an interlock system on the refuelin3' floor craneT The~iro7 pin; of a cask 'n the pool.is precluded by radundant ri;31ng. If a fuel bundle were dropped in the most sensitive area of t.: e fuel pool _ floor, which is the : inch by 3 inch area over t :e liner lea 4 fetection channel, and the leak detection valves were fully open, the ca xi nu, leak' rate souli.Se less than 70 ;silons per ninute. If tiese valves ihere then laft op an for thirty minutas, which"is siequate time for oparator response, t 't e canimun poci vater. loss vould le 210,0 gallons. !iis wouli rasult in a peel-level troe. of'less tS in 2.5 feet. 'e1 oval a n <i inst 211ation of 1 racks -luria; the olannad Tigh density soent fuel raci j j notification vill ie.oarforcea vich ri:;ing that vill pr2clude a -r2ch'Irop accident.

bocket 50-277/50-273- ?a;e 5 . Control o! 'ieavy-Loads ' ear Spent Tuel 4 a As described above, the p r o h a'? i l i t y of.s heavy oSjact Sein; dropied into the scent fuel pool snd causin; a loss of 3o01 inventory sufficient to uncover the fuel is ne3li;iils. "acuest _7 Oescribe_any design features or your Zacility *ih i ch affect t ': e potential'for a heavy lasi handlin3 s e ct ie nt involvia; spent fuel.:e.3., utili:stion of a sin 7,la failure-proef crane. 7esconse Peach lotton TS\\1 Supplement 1,

Response

4.9.i, Parts c, i, and e describes t'Te redundancy of the reactor buildin; crane, .the redundant rig;in; for the casi, and the a:inini s t r a t ive ~ c ont rols f r o 'a a used in movin3 tne casi. iacuest _3 ?rovide copies of all procedures currently in effact at your facility for the nove.nent of heavy loads over the reactor core du rin ref ueling, the <?ent fuel stora;e pool, or equiyuent required -f or the safe shutdcun af a plant that is operatin-at tha tine the move occurs. 1 "2soo,se 1 1 ?roceduras 7 ". - 5 c, T'i-19 4, T.la.7,-and

-17.2 are nttached.

':-17.2 joverns use of t'se reactor buildin; crane. '"-Sc 3cverns refueling a n i _ lo vi a 3 fuel. ~4-1?i aa8 3.10.7 jovern renov21 and reolace ent'of control roc Slad29

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Oiscuss tTe de;rse to *ihich your facility co 7 11as tith the ei :t (.').. r e gul a tory p os itions -delineated in 'e3ulatory Ouide 1.12

(?cvision 1,

Secenber, I?75).re;ardin; 3 pent ruel Stora;2 Tacility 7esi;nf!asic. '.e s m o n s e 4 1 "1e re;ulatory resitiona of 'e ;ulatorr ?uiie 1.12 (7evision 1, 7ect.iar11'73 2nd :he settas of t ta ?e:cl lotto-Init 2 3 ani J' spent !aal ?cols 11t' re: 2rr to the posicians Ira .li2 tad saquentially. 1 1

4 Sochst 5'-277/50-272- ?a :e 7 Contro1-af Heavy Loads lear Spent ?uel 3e ulatorf ?osition C.1: The spent. fuel storage facility ( i n c lu d in.; its structure a n d -. a quip ne nt excest as noted in pars:raph 4 below) sh ul" ae designed to O s t e;o r-f I seisnic requirements. 72ssonse: 'The Peach lottom spent f uel p ools are desi;ned in accordance with Tegulatory ?osition 0.1. As d e s c r i': a i in tha ?each 3ottoo 7sA?. section 10.3 and 3.ppendix C, the spent f uel p ools are designei and constructed to Category I seisnic requ'irenents. The pool is lined with stainlass steel and is designe! to p r ecl 2 de inadvertant loss of water fran the pool. 7o inlets, outlats, or drains are provided that 71 35t permit the cool to ba drained below ten f eet above the top of active fuel. Lines extending below this level are equipped with syphon breakers, check valves, or other suitabla fevices to' prevent 2ccidental pool draina;e. The above desi;n features will not cause the Suel to be uncovered through f ailure or nisoperation of connected systens. Te:glatory positions C.2: l The sacili'ty should be designed (2) t o '; e e p tornaite uinds and nissilies generated by these winds fror causine j significant loss of vctartight integrity of t't e fuel stora;e pool and ("a ) to Maep missiles =;enerated iy t o r n a rl i c ainds I-from contactin; fuel within the pool. esconse: The spect fuel pools at ?aach *otton are desi;na4 2' th substantisi c a p a':ili t y to. vith s t an t t ie effects of a to raado, : inclu ding t o rnado 3eneratec missilas. -Tiscussion of the cap 23111ty is provided in ??C Appendin J.f.2-and Supple-2nt 1, 2 u e.s t i a n 1.2.3 Additional inforuation is ?ravided in Topical '.e o o r t s AFID-5595, " Tornado ?rotaction ~for t't e Spant 7aal 7 t o r s ;e ?ool" (General ilsetric, 'o ve -b e r 115?) an! " Tornado Oriteria for :uclear ?cuer ?lants" (?echtel Corporation, July 1053). lased on t 't e above infor:ation, th2 'ea;i '.e t t e 1241 n 'meata '.e ;u la t o ry ?osition C.2. t 6 O ,--er__

'ochat 5d-277/fG-272 ?s;a-: Control of 9eavy 1.oais Year Spent "uel 7.evulstor" ?ositions C.3: laterlochs should be p r o vided to prevent cranes froc passin; over stored fuel (or near stored fuel.in.a nanner such : Tat if a crane.faila!, the load could tia ovar on storei fuel) uhen fuel handlin; is not in pre;ress. ? urin: fuel hanilin; ooerations, the interlocks may be bypassad and adniaistrative control used to prevent the crane fron carrying loads that are not necessary 'f or f uel aandlin; ove r the-stored fuel or other p rohibite d a reas. The facility shoul.i Se desi;nec to nininize the nesi for by7assia; s u c '1 interlocks. a Passonse Intsrlocks are provided to prevent the trolley, with a on its nain hook, from passin; over predetermined load the fuel pool. Strict administrative control is used for Sycassin; the interlocks d u r i n <; cash haallin; operations. Sea a ttached p roc adu re

.17.0.,

" ?.e a c t o r 3uildd 7 **ane Operation". 1. I Teiulator- ?osition C.a 4 A controlled leaha ;e buildin3 should enclose the fuel cool. The Su1111n ; sh oul d Se aquipp ed *:ith an a?;ropriate ventilation'and filtration-systen to linit tSc notantial release of raiioactive ioline and Other radioactive materials. The buildin-need not Se desi;ned ta iithstan? 2 nt r e me ly, h i fi vinds, but le14 age should be sui:1%17 . controlled durin; refuelin; operations. The lesiin of the ventila tion an d filtratinn syster shouli Se basel on the assunption tist the'cisidia; ci all of the fuel rode i r. ona f uel Nu n ila -ni th t be breached. The inventcry of r a d i o a c : i'r a materials avail 2512 for la aha r2 fro-the buildin; shoul-se issed on the=assunptions :iven in la;ulatory ? u i '. a 1.23 "Assunptions Tsai for Tvaluatint the ?otential la ii'13 ;ical Censequences'of'a Tuel 9andlin; Accident in the "nel 12nilin. ani 9torage 72cility for 2oilint and ?ressurizad "ater -2esctors"-(3afety Guide'21). 'esconsa The 'each lotton s7ent f sel s: ors 12 7cols ara lecate. in

Ta ra2ctor ;uiliin ; which sarve as secondary

~ containment for the reactors (saa 73\\? s2ction f.2). 2201-ratetor'$uildin; is 3esi:ned to contrel 121 : a ;c from tie Suiliin3 and pro'riiei filt stion, t ' c '. - the Stant>y 12s Tractnent Cysten, to:lini radio:::Lv2 discaar;as in :42 2 vent o! an.tectisat.- "entils tra 11: fron :32 s? eat fu21 ycol area is net n.'r ?.lly fil: 2rei

- c ~ 7 och e t: 50-277/37-273 22:e I - Control'of Heavy ~Loais 'iear ? pent ?uel i prior to enhaust-to the atmos?here (sas responsa to 0.7). -The StandSy Cas Triat:2nt Systes is descri$ci in .F S A.'. Section 3.3 3. The consequences and assuiptions used in-aval2atin~ a refuelic; sccident tre pressate.i in 7.; P. sections l i. ';. i i and 14.9. The analysis provided in section-11.~ uses conservative assumptions, sinilar to tiosa providai 11 2egulatory Cuiie 1.25, to demonstrate t' s t releases frac a postulated refuelin; accident result' in losas uhich are well uit' tin 10 Cr' 100 limits. Therefore, t re ?each 2 0 t t o r. le s i ;n haets Te;ulstory 'osition ~.L. 1 "stulator! ?ositions 0.5 b i The'spant fuel stora;e facility should hava at least : -.2 l of the,followin; provisions uith respect of tae handlint of ' cavy loads,'includia; the refuelin; cash: a 2. Tranes capabla of - ca rry in ; 't eavy loads should Se prevented, preferably 'ay desi;n rather than by interlocks, from movin; into the vicinity of t te pool; or b. Crsacs-should Se designed to p rovi de sin;1a-- failure-proof handlin of a c a vv, loa is, so that 1 5 sin;1e f ailu re till not result in loss of 3 canaS'ilit" of the ertaa-handlin: s y s t e., to parIer: 'its safety-function; or -c. The fuel pool should Se desi;ned to vitistani, iithout lesha;e that couli uncover the fu21, the i mp <1 c t o f - t 't e heaviest load te Se.cstried iy tie crane f roc tS 2 ca xi :u n h 21.;h t te vhich i t can Se lifted. If.this'approac% is usei, desi;a provisions sSculi Se ta le to p revent t* 2 crina, uhen carryin; ',eavy loads, f ro n.ovin ; la the ^ vicinity.of stored fuel. t e s c o r. s e The rain hooh an.1 itslassociitei lo2d lifti,; 2 2 t '. On .:S e reactor Suillin) criae are of a sin;1e failtre ; r ac! ' design such that a sin;1e failure vill not result in troppin; tha laid. Tha iesi,n is descriSe! in '3.V., Cup lanent-1,2estion 4...i. 22sei o s t' e above information, the ?cach lotton I?si:n me'e t s '.a 7 u l a t o ry ?osition 0.f.5. i 4 i 5 e ~ _ - ? e,r 7 -gWk T-- e-M r-4 ?wef-#3 +r-y f T

ocket 30-277/30-273

?a ;a l' Control o! '!aavy Lo:!s '? e a r - 3 p e n t 7uel i 1' Fosition C.6 Sa'ulstor" l -Trains, p e rmanent ly. connec t ed nech2nical or hyiraulic systers, and other features that by m.aloperation or fallar? i coali caise loss of coolant t't a t vo' tid u ncove r Iael shoull not be installad or includel in the desi;n. Syste-s 'or caintainin; vater quality an'd quantity sioull le :la si ;ne d s o that any maloperation or f ailure of such systens (includin; f ailures. resultinc, f ron the Safe Shutdoun Tarthquahe) 9111 not cause fuel to be uncovered. These s y s t e ns nesi not otherwise nest Category I saisr.ic requirenants. 'esconse To preclude the possibility of accident 1 irainin; of the spent fuel pool no drains are provided in the pool. A check valve and vacuun breaker are connected to each line outside the pool to prevent pool vater f r o., bein; syphoned out of the pool. Systens for e.a i n t a in i n ; aater quality ani quantity are designe?. so tTat any .naloperation or failure of suci systeas vill not cause fuel to be uncovered. (See response to " a ;u la t o ry Position C.1) ' e r u l a t o r -i ?osition C. 7-4 ) ?.clisble and frequently tested nonitoria; equipment shouli Se provided to alarn both loc 2117 and in a 1 c o n t inu ou s ly nanned location if the *: ster level in the fuel storage yooi falls below a predetarnined laval or if ti-h local-radiation levels are experienced. The :i;h-radiation- -. level'instrunentation should also actuate the filtration syster. 'esconse Since the fuel pool is desi 3ned to preclude the uncov2rint of the ~ fuel.a lovLlevel 212rn la not p r o vi d e ?.. The radiation levels-are nonitorad in the refuelin; . floor eniaust duct. i o t 's Low aad 4135 radiat1on s i ;n a ls { are alarned in the control roon aad a 'li '51 r2?istion si;nal isolates the duct .a n 2 initiates-the StandSy 2as Traatne3:~37ste9.- s \\ I I l ~' l i I i 1 -l i ij-'

Toc %at ;^-27 7 / 5 7-27 ' ?sca 11 3 u, o n t r o,. 3: .eavy.oa.s .aar,72nt .ue. 2 - e ulator- ?ositions C." 9 A seistic Cato;ory : ?.aSeu; systen s 'i o u l i ;e proviied to a -! coolant to the pool, b7ropritte redundancy or a 32c':up s; stem for f i lli n.; the pool fro, 2 relia'le source, such as a lake, river, or onstte seisric Ca ta ;o ry I v a t e r -s t o r -1 g e facility, should be providad. If a S s c:.u p systen is us22, it need not Se 2 p e r ?.a n e n t ly installad syster. Tie ct7acit; of su.olie! the na':eu p systens should Se s u c't that water c a n c ? at a rata determined by consideration of the leaicze rite t tat could be enrected as the result of d a.na ; 2 to the fuel ~ stors;e pool f ron the droppin; of loads, from the drc7 in: o? loads, fro-aarthquakes, or from tissilas o r i 'i n.i t i n ; in :i-T rinds.*

  • The staff is considerin; the d a v e l o c.ne n t of adiition.1 quidance concarnin; 7rotection anainst nissiles that

.t i c h t 12 cenarsted Sv plant failures such as turSine failures. ?ar the cresent, the protection of the fuel ecol 2;ainst suc1 ~ nissiles vill he avaluated on a esse-by-csse basis. 7es onse The spent fuel pool coolin; syste-oes not have a d seisaic category I source of .a': e u ? Jatar. "o1av2r, other sources of ma':eup vater 2re available to maintaia the spent fuel pool vater level. The availabla n a't e u ? unter sources and associated fic-r ates are li s t e d in the ' e s c'c ' o t t o., 7 5 1 '., Su,-lenant 1, luestion i.?.4. i ) 1

fRNl// <> + y,, k IMAGE EVALUATION NNN\\ TEST TARGET (MT-3) "g@a su 1.0 y DE I.I [" EM =1 1.25 1.4 1.6 6" MICROCOPY RESOLUTION TEST CHART 4 /<4% ?If,3,,p/// V,,?y5 b i.. - .: L ;,, w + = - =.

4 4 hYE'b, ih+# e+ V imieE Ev <uiriOs TEST TARGET (MT-3) l.0 E 818 EM y l" LE I.l [m lWM1 1.25 1.4 1 1.6 .i= c 6" MICROCOPY RESOLUTION TEST CHART 4ll% +%4 4g3x*f '4+ h 4 3, g, u.. L,._ w==_.x

f b M.17 2 Page 1 of b Rev. 0 JThinjj f W / W' w /h// D W.u.ALogoo L ....c. PHmnELPHIA ELECMIC COMPANI PEACH BOTTOM UNITS 2 & 3 l l i M.17 2 REACTOR BUILDING CRANE OPERATION 1 PURPOSE: l i I The purpose of this procedure is to describe the operation or the reactor building main crane. l l PREREQUISITES : l 1 Prior to any fuel handling outage, Maintenance Procedure M.171 is carplete. Maintenance Supervision Date 2. L80 V.A.C. power (bus 204-R-D) available to operate the crane. i 'O 3 The crane shall be operated by qualified personnel. During move-ment of spent fuel cask, drywell head, reactor vessel head or vessel internals, the crane shall be operated by qualified Maintenance Division personnel. TECHNICAL SPECIFICATIONS: None i SPECIAL PRECAUTIONS: 1. NO SPENT FUEL CASK MOVEMENT SHALL BE PERMITTED OVER THE REACTOR WELL, ORYERld'ARlTOR STORAGE ~WELL, OR SPDIT FUEL POOL OTHER THAN THE CASK l. LOADING AREA. 2 MOVIMENT OF THE DRYWELL HEAD, REACTOR VESSEL HEAD OR VESSEL INTHUIALS OVER THE FUEL POOL IS PROHIBITED. SPECI AL TOOLS : None lf REFERE' ICES: 1. Instruction Book 6280-M13B-28, Whiting Corp., Operating Instructions. 2. Whiting Corp. drawings, Bechtel Foreign Print Nos. o250-M13B-35, Mr6Ecit1ThrWLJ4%!r6cEL10ERLl4ATr6L-rR3hRL

M.17 2.

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h Page 2 of h Rev. 0 PROCEDURE: 7 1 See Whiting Corp. Instnaction Book 6280-M13B-28, Reference 1, Print No. U 60327 for location of cab and pendant controls. 2. TO PREVENT ALL GANE MOTION IN AN DGRGENCI, PRESS "SIOP" HJTTON. 3 Maximum crane speeds are: Main hoist h.5 fp Main hoist using inching drive h inches per minute Auxiliary hoist 23 fp Trolley 10 fp Bridge 50 fp h. To prepare for operation a. meck to see that all cab control handles are in the "0FF" position. b. meck to see that switdt "MHC" (The (2) lube oil pumps switch) on the trolley is in the "0N" position. c. Place the " Cab-Floor" selector in the " Cab" position to energize cab controls. This will de-energize pendant controls. d. Place main breaker switch, 20h-R-D, in the "0N" position. e. Press the " Start" button and observe that the red " Power-on" light indicates power is on. 5 To operate crane All controls are the stepped type with five accelerating points a. in each direction. Higher speeds are obtained as controller is O advanced to each point. Depending on load, motion may not occur at first or second points. Always move handle slowly through each speed point, both' starting and stopping. DO NOT OPERATE CONTINUOUSLY IN THE FIRST, SECOND, OR THIRD POSITIONS AS THE EDDY CURRENT BRAKE WILL OVERHEAT. t. Main and auxiliary hook operation (1) To raise hook, pull control handle toward you. (2) To lower hook, push control handle away frm you. (3) To stop hook, return control handle to the "0FF" positien, autcmatically setting the electric brakes. (h) Main hook limits - if upp'r limit switch, lower limit switch (at El. 2378), maximum load limit switch (approx. 120 tons), or minimum load limit switch (loss of hook weight) are actuated, main hook motion will stop. Following limit switch cperation, motion is only pemitted in the opposite direction. Motion over the spent fuel pool with any load on the main hook is prohibited by the key switch interlock. (5) Auxiliary hook limits - if upper limit switch or lower limit switch are actuated, auxiliary hook motion will stop. Following limit switch operation, auxiliary hook motion is only pemitted in the opposite direction. O

~ V, ( ) M.17 2. page 3 of h Rev. 0 m (6) The main hook has an inching drive. To use the inchinc drive, place cab selector in " Slow" position and use main hook control in normal manner. Main hook mmh =um speed is 4 inches per minute. (7) If the red rotating light on the trolley is actuated the main hook is tilted to one side. Lower the load and balance evenly. ACTUATION OF UNBALANCED IDAD LIGHT CAN ALSO INDICATE CABLE FAILURE. INSPECT CABLES BEFORE FUR W ER OPDIATION. (8) If crane trips off (" Power-on light goes out and crane t stops) check the followings (a) Loss of h80 V.A.C. power. j (b) "Stop" button was accidentally used. (c) Hoist overspeed trip has operated. LOSS OF POWER COULD BE CAUSED Br OVERSPEE TRIP OPHIATION. THIS INDICATES EQUIPMENT MALRINCTION. DETERMINE CAUSE OF THE TRIP BEFORE CONTINUING OPSIATION. c. Trolley and Bridge Operation (1) Advance control handle in desired d'.ection. (2) To step trolley motion, move handle to "0FF" position, p automatically setting electric brake. (3) To stop bridge motion, move harxile to "0FF" position and apply foot brake. BRID0E MAY DRIFT IF FOOT H1AKE IS NOT APPLID. (h) P.estricted area operation - (a) The key switch interlock must be actuated to move the loaded main hook over the spent fuel pool and further North and West. If the hook with a load is moved to the beundary of the restricted area with-out operating the interlock, the crane will stop. To move away from the restricted area the interlock must be reset using the key switch in bypass until the main hook is clear of the restricted area. TO MOVE A SPET FUEL CASK INTO THE CASK LOADING AREA 0F THE SPENT FUEL POOL, THE KEY SHALL BE OBTAINED FROM SHIFT SUPERVISION. NO OTHER ACTUA" CON OF THIS INTHILOCK IS ALLOWED WITHOUT PSIMISSION OF STATION SUPHIVISION. d. To operate +he crane with the pendant (1) Check that the " Cab-Floor" selector switch is in the " Cab" position. (2) Press pendant lowering button mcmentarily. The pendant will lower to elevation 2h08 and stop.

(T D M. n.2. Page h of h Rev. 0 ^ (3) Place " Cab-Floor" selector switch in the " Floor" position. Crane is now controlled frca the penf. ant, and cab controls are de-energized. (h) Use appropriate pendant control as labeled to control j crane and pendant. Pendant can be raised and moves East and West from the pendant. Bridge, trolley, main hoist, i l and auxiliary hoist control is five speed. CONTROL OF MAIN HOOK FROM THE PENDANT IS PROHIBITE. WE IRIDGE BRAKE CANNOT BE CONTROLLED FROM WE PENDANT. ) Press "Stop" button (de-energizing crane nid setting bridge e. electric brake) and place main breaker 20h-R-D in "0FF" position when not using the crane, l IN-PROGRESS INSPECTION _ None TESTING: Periodic preven'ive maintenance shall be done in accordance with 8 Maintenance Procedure M.17 2. REWRN TO NORMAL: Not applicable. i t l

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W/y/7 Y r 4 a Pl!!LADELPl!IA ELEC1RIC COMPANY Peach P.ottom Units 2 and 3 FJi-6C FUEL MOVEMENT AND CORE ALTERATION PROCEDURE DURING A FUEL HANDLING Ou RAGE PURPOSE: This procedure provides instructions for fuel movement and for special nucleai material = accountability. Along with other procedures for performing core alterations other than movement of fuel assemblies, this procedure provides instructions for core alterations and means for documenting the core alterations. This procedure does not provide deta!!ed instructions for core alterations other than movement of t'uel assemblies. This procedure and 4 its accountability requirements apply to the moveEUNT of all core components in the fuel pool during a fuel handling ' outage. Procedure FH-35, Fuel Peol Accountability, covers movement within the fuel pool when this precedure (Fil-6C) is not in affect.

REFERENCES:

P-1. S-II.) Operation of the Refueling Platform Control.s and Interlocks. 2. Procedure A-44, Special Nuclear Material Accountability. 3. Procedure S-14.2, Moving Fuel From the Fuel Pool to the Reactor. 4. Procedure S-14.3, Moving Fuel From the Reactor to the Fuel Pool. 5. Procedure S-14.4, Moving Fuel Within the Reactor. 6. FCAR Appendi: A, Technical Specifications and i<av '7 GEE 90S 1, Volume VI, Service and i:andling Lyuip: rent. S. - S-11.3, Renoving lilade Guides from the Reaet.*r :ia.i l'lacirg th m ir. the Fuel Peol. 9. S-14.6,. Removal anJ Installation of a Fuel Suppert Piece. 10

3. la.6A, Re' eval o f a Fuel Support with Pa:-t ia l !'.

Inserted CRD. ' ll. S. l 3. - Removal And Installation Of A Cor.tre! %d, 12. S.1 ;. '. A, itenova l-o f \\ P :rtia l ly incer uJ Con'.rel ? D 13. S.14.3, Fuel As, ]hly Ree : anne li n,:. am w -w y 7 -e

1.1-6C Page 2 of. 9, Rev. 14 M-4.6, LPR!! 'lemoval and Installation Procedure. ~ 15. M-4.7.1, Installation and Removil af the Fuel Loading Neutron Scurce. 16. M-4.7.2, Installation of the Operational. Neut ron Screes. PREREQUISITES: (Each item below must be initialed as completed.) CHECK-OFF 1. Reactor mode switch locked in' REFUEL.. 2. All control rods fully inserted, except as specified in Technical Specification 3.10.A. 3. Refueling equipment and interlocks functionally tested: Procedures FH-21.1, FH-21.2, FH-21.3, FH-21.6, FH-21.7, ST-12,1, M-4.8, and M-4.20 completed. 4 SRMs inserted, functionally tested, and operable as required by Technical Specifications 3.10. ST-3.1.2 completed prior to core alterations. 5. Spent fuel pool full and fuel pool cooling system operable. 6. Contral room emergency ventilation systems operable. 7. Standby gas treatment system operable. 8 S. Secondary containment established and containment isolation system ope rab l e. (Required only when irradiated fuct or a fuel cask is being meved in the reactor building per Tech Spec 3.i.C). 9. Standby liquid' control system operable. 10. Core and containment cooling system capability provided as required by Technical Specification 3.5.F. 11. Continuous and reliable ecmmunications established between control room and refueling platform operator. <!2. itefueI tn.; floor access control estah1ishing and R',.P i: sued, if required. 13. fuel preparation machines functionally testeti, if necessary for work, M-J.17 and Fil-21.1 IJ. Core preal t erat ion inspect ion complete, Fil-ll.

15. " Fuel movement tag boards have been ehecked te preciale assembi;.

l oc n i on. If. ' Care.Compnnent tran:fer-aathart:ation sheets Fil-cr are nrrvided in

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O~ ' Pefueling bridte-(l'ael llandita; c pc: :sar* a Reheling ficar i.\\cennatabili ty Techn:;in i Centrol Re.m. (Assistant f:ontr. ! CperaMr

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c. Sha1! direct.nd supervise alI cpu a M rs U ;i: nN c .he te: :e1 t" o. rent of an chr - crent m; i n, -: e. '. ! ..aae acco:<, t b. '..I h in.i! :n. r.cr i3or 31.a ; ! ,e' rm i a t ? r. .'.er ,ocreeti. .:e' inu and so inst act ti.e fuel :tandlina e r t t.. o ' b ill I" resronsible t'o* the .!v'i n of !e r. .in-p.it rm g. iaspcetion cheek-list C.O.L. 1:: !- tJ prior t;. ini..

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an.1 34 ca r l:. a s practie.;bie on sub:eq e.:t sh:fts, tue week!- re: 2el p l a t fi" :t sur.eillance test ( S f - l _'. i ). daily "R"

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8 test -i-3.1.2t and review o f t he p re r e i.u ' s i t, ti ht-nroc' dure. 2. !ie :l th I'hy - !es Qual ified P 'rsonnel .i. Ga l l ':en itor t he ' des igna t i controiltd access areas. b. Shall periodically inventory the protective clothing supplies and replenish as found necessary. e. Shall provide step-off pads, trash receptacles, personnel monitoring ind u4cd protective clothing receptacles. d. 'ha l l ; rov itie H'..i's for "a: :cus tasks being performel en the refue!,n; f lee.: e. S:iall provide, inspect, and maintain cont.mination contro! areas. 3. .\\<sistant Control Operatar a. Sha!! bt in direct ce::rtunicattan.,ith the reineline platform optrate: and shall :naintain the fuel t ransfer. lata sheet s, r!!-oC. h. Sha:1 e. nt i nua lly ol'4erve the S!31s duri n.g care a lt.ra tions t a alert -he refueiin: plat form operater :f abnorna! resp;nse \\ce : int.ibi l i t y Technietin p i. ul1 'b crve 'he at: neri:ed ecrt component rovements 1"<'cifi;d on t : :: re S r att! '.ar i :a t i e!) -heet s fil 8v: l'. .eing fe11r,.ed 1'- 3 ":I ni'"" ! ! traas!

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the Fucl lianlf i ne Supervisor). 6. Reaeter I ncineer (or designated alternate) a. Shall be responsible for matntainine the fuel acc ountab i li t. files and ensure that the fuel accountiag data sheets necessar 13 proper 1 recor:I fuel movements are ecaplete and accurate o b. Shall make a frequent inspectica durine fuel handl:nc rperations c: t 5-fuel transfer and accountability records. c. Siiall advise the accounting technician on fuel accountine methods and procedures. 1.nsure that unresolved procedural problems are presented to the P.O.R. Committee for resolution. d. Shall provide authori:ed Core Component Transfer Authori:stion sheets Fil-6C to the Fuel llandling Super'. isor, Assistant Centrol Operaler, and accountability Te hnician. COR F CO?lp0'.1:N I KCCUN'l I.'.'G fhe fuel pool and reac t,)r ta g hea rd, chall be at.atcj shene..' a fuel a s s er.b l:. is relocated. 1 he t'ue l hand i i nn super'.- i eer e5all be responsib le :e dirceting the updat ing of the tag boards. The Core Component Transfer \\uthori:ation Sheet Fl!-oC is beth a schedule and an authori zat ion f or t he relocat ion or t'uci as"embl:ee. or tne perforrnince of ether eere alterttions. The cheet will d;r.et and guide the fue! !.and ii:.c super,: or la scheu,uling retuel rioor werk ana. :n nertorning sate an, effi;ient fuel han !!ing operat ions. !he cer" i n the cant rol reem.<ill e i chee; that tht fue l moveme'n s.aeJule is beinc ru!!m ed. The sht et C;' .1 '. l'e us e.; to record t he !ir e ind date Vien ecch fue l necement Or other ce a l t e r-'It i 'n i s pel' r Kd. 'r; pared Core fo7p." at ei, ~ 21 \\;;hCT!!at! ' L 1. 3 hall b'. 3: :')Cd bi t h . c '.C t a r Ligineft ar hi a ltern it ' i the 3 pace "iUTl!OR i:: !' Ev." U n w 5.' i : e t' Core C,";'c nen t Tru'ft. \\utheri at: n - - Et!_:.c 5ai1 a r S. usec. 5 a n.,e e to-herm- 'd .,r"it Tr -~.'- "W

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... + i ali c a t. r-a si:..:a! ut tu- ok" ma:t be v ..:lly r.ri e!< ed or' to o i liftim; a fuel e l e:.;e n t or bladt giide A;: a. c. c. h :t b>.. ts ia.. r::pple and not e a:y:h t an a corne tue e c the ~ue! rrap; ' e he.s posi t ion inlicator 1 : c, h t 'ut in ene' i:ed irt d t p. ti. lifti.e i fuel in.ndle ar blas:e, mic. Uten th fa. : ban i! a . i f; the 1:. ht ti]1 ,a out. d. l 'ie ;r ipp le opera ta r t!:!ST not wit h the Jepth irdicator wht, the fu e ! bundle is approuehing the upper g -id or the top af a f':ei storat;e rack or when the fuel grapple is approaching a fuel bundle er blade guide. The grapple operator MUST always watch the fuel bundle. e. The refueling platforn shall be inspected pe: C.O.L. EH-oC and tne inspection report filled out prior to the initial fuel handling shift and as early as practicable on subsequent shifts. f. the rapple operator ea:- chale the grapple whc n tne fuel asse bly : s g o i m.; into'the core; this wilI help prevent the & el assc..biv from h a n g : n.: up en tne uppe: gr i d or b lade t:uide, g. Periodically check the distance between the fuel asserr.biy picce ar the cat t le ehnte to cer:t'y that t he fu l ! u;' Iinit switches have n> slipped The refue li a.; p la t for"1 Operator e:tn 3heerce this when fitel is heine bro'acht tbrungh the eatt:e chute it. i.enn 'he fin'i .t e seatb ly away f r u '1 the center o' t h e c'.' l l the last : ' ' ' of '.-e: tio, te protect the sprin.: elip. 1. Tiir T3 ,i'isl ir.l:"c :T':l!l! ed.tu \\ ; i 1:1 r.

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4-Page <> of 9,-Rec. t I iM ITATio:: !M COV! It.l!!.il Hil.L Mll!! '_.T: l. The to.. e f comminii ca t i on. be t t.een t !w Ces t i o f Rw.. ud the W fueiing i'..e. shall bc reason to terminate fuel 1:o. itns ope m ians a'itil evemun:e.ition i _ restored. 2. The t.,alfunct ioning or failure of ncce than the or t he sourc e i...: n :.o n i t o r s or interaediate range monitor 3 shall be reason ta t, minate : ore atterata ns. unti! problem is corrected. 3. He accidental dropping or danaging of a fuel assenb!v during the handling operation shall be reason to terminat fuel han!!ing operations until the exact nature of the danap to the subject fuel assembly and to surrounding fuel assemblies snd core components i4 d et ermined. Authorization to continue fuel loading following an accident of this nature shall be obtained from the Plant Superintendent. 4. If any system or equipment prescribed as a prerequisite to this procedure becomes ineperable, discontinue the fuel handling or core alteration operations until the required system or equipment is returned to operation. PROCEDURE: ALL CllANGES TO TilIS PROCEDURE CONSTI'IUTE TEMPORARY PROCEDURE CllANCES A?.D MUST BE APPROVED BY Tile SilIFT SUPERINTENDENT AND ONE MEMBER OF Ti!E PORC PRIOR -TO MAKING Tile CHANGE, PER PROCEDURE A-3. 1. Contact the station Shift Superintendent; verify prerequisites to this p procedure are satisfied. 2. Obtain the Shift Superintendents' pernission to begin fuel movements or other core alterations. STEPS 3 THROUGH 6 APPLY ONLY TO ME MOVEMENT OF FUEL BUNDLES. REFER TO WE APPLICABLE PROCEDURE FOR COMPLETION OF OTHER CORE ALTERATIONS AlRHORIZED BY CORE COMPONENT TRANSFER AUTHORIZATION SHEETS FH-6C. 3. .Beginning at Step l'of Core Component Transfer Authori:ation Sheet FH-6C and proceeding sequentially thereafter, move the refuel bridge and grapple to the designated location. Lower the grapple to approximately six inches above the assembly. Verify the asser ly serial number corresponds to that number designated by the authorization sheet. Serial number verification for moves from the core to the fuel pool may be delayed until the assembly is released in the sipping can, storage rack, or fuel preparation machine.. If the serial numbers _ cannot be read in the sipping cans, fuel rack, or fuel preparation i machine, verification will be done by procedure Fil-12, Core Verification, following completion of fuel movnents. Serial numbers of ass-mblies in the fuel pool will be verified following completion of fuel movements. 4. With m open grapple hook, rotate the grapple to provide the grapple-to-assembly orientation designated by the Core Component Transfer Authorization Sheet FH-6C. Lower the grapple onto the assembly bale anc cIese the hcok. Verify the hook-closed indicating light is illuminated and the hook bale is O in the closed position. P

...-w f 9 Page 7 of 9, Rev. I l 5. I n fo rni a s i s t a nt cont ro l room w...tiir Of i nt ende ! 'uel move and obtain le r i t'i e:lt 10n t }l.I t t}ie hlIII' 's are he re Observe.' l'O r.PVe5 inte Or Out Oi the Cure. 6. 1.i f t a:ni triaist'er t ne.i.: N:h : ' t o ' h.. leh.t i <n. t.d 1.: t.;e Core Cor. pon en t Trans fer Au t h.> ri :a t i c.i. *:het t, I li-h F.. Re rt t i.. 3 t h.: control roon., recor ! the move on C..rt Cor'pon.:::t : ..fr. '.u t :.ci ..r. Sheet Fil rC, and adjust *:tatus l'oard islent i fi c:. : i a.t t..,s t u refitet t:te I.".0V C. 7 P,ep ea t Step:; 3 through o for all srtis on ibr-t?.i upo:ie.:t Trav. er Authori:at ion Sheets FH-CC un;i1 :ll1 Zore il tot ati nu .rce e - are completc. r l l 1 i O L

'J 's. % ? N'?u l ETAD IED T Ti l CC CE AT O L S O CA C I' 6 Vi l Fi TE E Y N l B S O i .I 1 0 0T E 0A Z PC N I O O R L 0 I T i OR t A T TO Z U E I A T } R A N O D O I EI IT J RT OA IA CC R O L E f F o T SN N E A I R R T 3 TN E E N N N G O O O A I LI P I P S OT I OA O V PC C E O R 1 L E 00R R O RO F C E C N N O E EI J t RT Q OA E CC S 0 I L A o I RN L S ~ P ~ Eo TN S

cl.-vL $I 1$ Page 9 of 9, Rev. 5 C.O.L. Fil-6C REFUELING PLATFORM INSPECTION AND SRM CORE MONITORING CllECK O 1. Make sure tracks are clear of all debris. 2. Air compressor on with pressure ---100 psig make sure water-trap is empty. 3. Fuel hoist cable and auxiliary hoist cables (No cracks,-Main iloist frayed ends, etc.) (Not required if not in use dur ng -Monorail i shift). -Frame 4. Verify indicating lights for " Grapple Normal Up", " Slack Cable", " Hoist Loaded" "floist Jam," and " Grapple Full Down" are operational. (Bulb Check Only). 5. Up limit switches working on auxiliary hoists. (Not -Monorail required if not in use during shift) -Frame 6. Check power cable reel feeding platform for proper operation. 7. Check phone cable reel feeding platform for proper operation. gag 8. Verify power cable support rollers feeding operators cab are all on steel cables and working freely. 9. Verify platform position indication drive wheels are on chains and tracking properly. 10. Inspect grapple sections for proper movement and uneven wear. (Not required if not in use during shift). 11. Inspect grapple latching mechanism for proper operation, loose bolts, etc. (Not required if not in use during shift). 12. Perform general bridge inspection, checking for cleanliness and loose hardware and verify operability of monorail and trolicy hoist. Check for any nuts and bolts that might have vibrat-loose. 13. Grapple air brake pressure 70-80 psig. (Not required if not in use during shift). 14. Inspect track limit switches (refueling interlock) to l ensure satisfactcry operation and physical integrity. 15. ST 3.1.2 SRM core monitoring test completed prior to making any' core alterations and daily when required to be /") operabic. Date: F Time:

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^ q f' s! M - A A. ArN J/.}/?& e i i e PHILACELPHIA ELECTRIC C SANY PEACH BCTTOM UNIT 2 -FH-19A CHANGE-OUT OF UNIT 2 CONTROL ROCS 46-23 I. PURP3SE: This procedure provides instructions for the change-cut of control rods in locations 46-23 of the Peach Bottom II core. II.

REFERENCES:

FH-14 Fuel Movement Procedure: S.14.5 Removing Blade Guides frcm Reactor. S.14.6 Removal and Installation of a Fuel Support Piece peg S.14.7 Removal and Installation of a Control Rod Technical Specifications Section 3.10 S.4.2.G Returning A CRD to Service... S.4.2.H Blocking A CRD... III. PREREQUISITES: 1 See applicable parts of procedures 5.14.6 (Remeval and Insta11atien of a Fuel Support Piece) and 3.14.7 (Removal ind Ine:311ation of a C:ntrol Rod) for the necessary prerequisitec. IV. AD'.'Irl! STRATIVE ' CONTRCL S: It'is essential tha: the control room thit: :up r/isor be kept informed of all ~ aspects of the change-out from the time the cid rod i; withdrawn until the new rod is incerted. It will be the centrol room shift supervisor's responsibility to see that the control ruf drive involved is preperly valved out and blocked to prevent incertion during the work, and to see it is unblocked and valved in as required. (Refer to procedures S.4.2.G and S.4.2.H f : v11ving precedures). /*%

EH-19A Page 2 of 6, Rev. 0 D. IV. ADMINISTRATIVE CDNTO St (Ccntinued) Special Tech Spec requirements _ applicable to this procedure-are: 1. Mode switch locked in RSFUEL-2. The jumper which indicates rod-fully inserted may not be installed until AFTER the fuel is removed from that cell. 3. No fuel may be reloaded in any cell until ALL control rods are fully inserted. PREREQUISITES: 1. See applicable parts of procedures S.14.6 and S.14.7 for general prerequisites. 2. Mode switch locked in REFUEL. SS/SSV__ e t;ame/Date 3. Blade guide must be complete prior to performing prerequisite 4 In accordance with applicable parts of procedures S.14.6 f=s and S.4.2.H, withdraw and block control red 46-23. Inform SLO on refuel flecr prior to rod withdrawal. SS/SSV Name/Date For each control rod, jumper P1-A to P1-N to give a double 4 zero (00) indication and jumper F1-V to P2-W to lite the green backlignt en the control room RPIS display. Leg all jumpers in the unit 3 jumper log. SS/SSV Ma.me/Da te V. PR3CEDURE: 1. Notify control roem shif t supervisar of intention to start work.

2. _ Remove fuel support piece in location 46-25 in accordance with applicable parts of procedure 5.14.6. (nu te the in-vessel rack will not be used for.this work.

A'apecial rack capable of holding 4 orificed fuel support:.;111 r<. used to hold the 3 orificed fuel suppcrts taken out ateve. T.e : ntrol red stcrage racks in the spent fuel pec1 will be used to store centrol reds). Flace them in the : tera:o rack a: ahcwn in figure FH-19-1. _O ~ 3. Remcve the control rod in 10c.itier. 46-23 in se:Ordance with the applicable part; of procedure 3.14.7.

E917 A F): 3 c: - rj, hev. C 1 I V. PROCECURE. (Continued) NOTE: -THIS BLADE IS ALREADY U!; LATCHED; CO NOT UNLATCH AGA 4 Store the old control-rod in spent fuel pool location B15 5. . Record the serial number of the nesv rod ~ on data sh 6. Install new control rod in location 46-23 in accordance 4' i . applicable parts of procedure S.14.7. with 7 applic' ble parts of procedure S.14.6. Install the original fue a the blocks on the. control rods, installing blade guides (This includes i fully. inserting control rod. , and jumpers installed in prerequisite 4This will require removal of the-after removing jumpers. Sign off the jumper log 8. The final configuration of the cell should be as in t'ep 1 control rod fully inserted, blade guide in place, nc fuel in cell. m' i SS/SSV. a Name/Date 1 9 I i 4 .k e w ~ ,,,m-.n, n -r_ _. - -

t.=' hi l'4A V1.- a o f u, Rey, O 5 + DATA ~ SilEET FH-l'4 i Old-New Control Control Rod Rod i Serial Serial Date Loeation t; umber Number Cnanged Co.ments 46-23 i A 6 I t -~1y--- p 39-9+ .<m--r---w +--'Me 7 T- -1' s-- e<w

-I r i t: m .eac*.or Cuvity I, i .:a Fig. FH-O

N ',, W P.C. No. I3-19A 'm ; #'h. INSTALLATION 0 t -: - 17 y

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'.'i AND SERVIG WORK PLAN CHECK LIST P39e ' of 6 y p ,:.i'ci ENGNEERNG r-w J. ? f 0 DEPARTMEhfT - p,,,cs.ao,e o, .-ro Ict Pe s c h Bottom tin i t 2 Project No. _ Work Plan No. IN-19A O R ev. Production approved by/date 7/8 M Yr 26 Prepared by/date D. Tor A n ' hb##{ $ 3/7b Customer approved by/date - "#2 2 -- / /74 OA approved 5y/date /r i 11 s v w nc n rm es OC Procedure or Special Process efer ompliance Seq Operation Examination or Test Instruction & or Joint Process Revision Control Sheet canon By & Date By Date VI QC to monitor control rod SPCS O N A D 1 change-o.tt operations and JPCS C thr n recording of data 9 No._ to Total per seg. SPCS O N A O JPCS O No._to Total g per sea. SPCS O N A O JPCS O No. _to Total per seg. SPCS O N A C JPCS O No. _ to Total 1 per seq. ~ ~ SPCS O N A O JPCS O No._ to Total per 500. GENER AL h ELECTRIC

l ~ o OO ~ . 1.., Page 1 of 4 r Rev. 1 WP.hls $ N!8 Y //.a r/n . __ w. PunAngIERIA ELECTRIC C43fANY PEAG SOTTCaiINITS 2 & 3 S.14.7 EIBENAL AS IESTALIATION OF A CONTROL BOD PURPOSE: This procedure gives detailed instructions for removing a control red, either latched er unistaked to the control rod drive, from the roaster eere, far patting the control rod into a control red storage rack, and for returning the control rod from the storage rock to the more. PtpB5@ISITES: 1. Maintenance Esquest 7 bra and Radiation Work Fermit imh. P 2. Fuel support piesa removed free the guide tube per precedure 3.14.6. 5 3. If the oestrel red drfwe has been removed, a blank flange must be installed on the CBD housing flange to prevent reactor water from running out the bottom of the reactor. This flange must have a drain valve with a hoes attached to drain the unter from below the control rod when it is reinstalled in the boek-seated position. 4. All required special handling tools must be functionally checked-out prior to use. Theck all air fittings, both on the tools and air hoses, for leaks by submerging them, or test with anoop. 5. All spesial tools checked for cleanliness. 6. Ca e tions betueen the control room and refueling platform provided and fuantiesing. 7. Control red position indication available in the control room. 8. The control red guide tube seal must be removed, if installed, prior to installation of the control rod. 9. Emmeter abetdeus, depressurised, and prepared for fuel handling per M.4.1, M.4.2, M.4.3, & M.4.4.

10. Fuel peel gates removed from the fuel pool reactor canal and placed in their storage locations. Reactor cavity flooded per s.7.2.E.
11. Reacter ande switch lockad in the REFUEL position.
12. All control rods other than the one being removed fully inserted except as specified in Tech Specs. 3 10 and 4.10.

13 Jamming button (clam}'I attached to the monorail hoist cable so the hoist ( cannot be raised above its normal up position when raising any reactor internal component or radioactive equipment.

14. Tech. 8peos. sections 3.3, 4.3, 3 10, & 4.10 reviewed and complied with.

Confirmed by

A 9 5.14.7 Pago 2 cf 4, 1sv. l syBCT_AL PRECA'ff1W88 Whenever moving a special grapple into or out of the top grid, 1. monitor air hoes condition eo that it does not slacken sad jam between tbs top grid and grid guide. 2. When not in use the main fuel grapple must be at full-up and the seniliary hoists must be a full-up on boist override and all special toals must be removed from the hoists. SPECIAL TOOLS 1. Grid Guide 2. Actuating Pole 3. Control Bod Grappia 4. Control End Onlataking Tool 5. Blank flaags 6. Guide tube assi

REFERENCES:

1. G.E.K. - 9684 Volume II, Instruction Book 628Hn-{J-102. 2. G.E.K. - 9684. Velues VI. Instruction Book 6280-M1-JJ-109, 3. Proceders 3.4.2.0. 4. Procedure 5.14.6 FROCEDuki' THE FIRST SECTIM OF TEIS PROCEDURE APPLIES TO THE RIDCVAL OF A CMTROL EW IATCEED TO A COIrfEOL ROD. 1. Completa steps 1 through 18 of procedure S.14.6. This involves removal of the 4 fuel bundles and fuel support piece associated with the sentrol rod being removed. 2. Remove the fusi support piece grapple and grid guide and attach the control rod calatch'ing tool to the monorail hoist. Cheek the unlatching tool for proper operation and the air fittings for leakage. Frees the DISINGAGE button to ensure that the tool is in proper position. 3. Attach the actuating pole to the stud at the top of the unlatching teel, to provide positive control of tool. 4. Iower the ualatching tool through the top grid and over the control rod until the control rod handle is abated against the lower plate of the latch tool, and with the latch tool stringer located at tbs junction of two blades. 5. When the cable is slack, check that the unlatching tool is properly seated on the control rod by pushing down on the unlatching tool with the actuating pole. 6. Press the ENGAGE button to grapple the handle and unlatch the control rod from the drive unit. Manually try to raise the control rod unlatching tool to ensure that the control rod has been grappled.

O 'O s 24 7 Pago 3 of 4, Rev. '. / / TER F031T105 DISFLATED FOR THE PARTICULAR CONTROL ROD IN THE CONTROL RO W IWST BE IGNITORED DURING THE PERFORMANCE OF TEE FOLIAWIEG STEF. IF, WHILE PERFORMING THE OPERATION DEStstaarn. TER INDICATED ROD FOSITION CHANGES TO A LOWER NUMEE, THE CONTBdM. 300 IS NOT UNC00 FLED. IF THE CONTROL BOD IS NOT UNC00 FLED, IBGEDIATELY HALT OPERATIONS AND AGAIN ATTDWT TO UNIATCE. DO NOT ATTEbeT TO BBWVE A CONTROL ROD WIIBOUT VERIFTING THAT IT IS UNCOUPLED FROM THE CED; SERIOUS EQUIFIENT D& MAGE COULD OrEEE WISE RESULT. i 7. Raise the esatrol rod through the top grid to the full-up position of the heist. 8. Move the refueling platform to place the control rod into the invessel rack or into the fuel pool and lower the control rod into a control rod storage rack until the hoist cable is slack. 9. Press the Df - button to release the control rod. Mammally attempt to raias the tool to ensure it is unlatched and than raise the heist slowly to its full-up position. TEIS ClarLETES TER RE3ENAL OF A LATCBED CONTROL BOD. THE BEER SECTIN OF TEIS PROCEDURE AFFLIES TO RDEW4L GF AE UNIATCEID O WISOL 300. THE CRD M&T BE EITHER IN PIACE E BEMNED.

10. Cosolete steps 1 through 18 of procedure S.14.6.

This involves removal of the 4 fuel bundles and fuel support piece asaoeisted with the esatrol rad being removed.

11. Rameye the fusi support piece grapple and grid guide and attash the control rod grapple and grid guide to the monorail hoist.

Check the grapple for proper operation and the air fittings for leakage. Press the DISENGAGE button to ensure that the tool is in proper position.

12. Attach the setusting pole to the stud at the top of the grid suide for positive control.
13. Iower,the grapple through the top grid and over the control rod bail until the hoist cable is slack. The grapple must be aligned so that the grapple hook will engage the bail.
14. Press the ENGAGE button L grapple the handle. Manually atteset to raise the control rod grapple to ensure that the control red has grappled.

THE POSITION DISPIATED FOR THE PARTICUIAR CONTROL BOD IN THE CONTROL ROON IWST BE 3GNITORED DURING THE PERFORMANCE OF THE FOLIMf!EG STEF. IF, WETLE PERFORMING THE OPERATION DESCRIBED THE INDICATED ROD FOSITION CHANCES TO A LOWER NUMBER, TER CONTROL ROD IS NOT UNCOUPLED. IF THE CONTROL 200 IS NOT WCOUk1ED DetEDIATELY HALT OPERATIONS AND IDWER THE CENTROL 90D AND RELEASE IT FROM THE GRAPPLS. DO NOT ATTDIPT TO RIBENE A CONTROL 20D WIIBOUT VERIFYING THAT IT IS UNC00 FLED FRiat THE CED; SERIOUS EQUIPMENT DAMAGE COULD OTEIR WISE RESULT. (

15. Raise the control red through the top grid,to the full-up position of the heist.

f] S.16.7 Page 4 d 4, Rev.

16. Move the refueltag platform to place the contal rod into the mve: 4M r-or into the fuel pool and lower the sontrol rod into a control ro<1 storag.-

rack until the hoist cable is slack.

17. Press the DISENGAGE button to nisase the control rod.

Manually atrampt to raise the grapple to ensure it is released and then raise the hoist slowly to its full-up position. TEIS CCIA'LETES TE REMNAL OF AN UNIATCHED CONTROL B03. THE MEI! SECTIM OF THIS FRJCEDURE APPLIES TO RETURNING THE CONTE 0L 300 FBial TER FUEL 700L TO THE REACTOR.TE7.S AFFLIES WITRER TER CED IS IM PIACE OR NOT.

18. Attack the control rod grapple and grid guide to the monorail hoist. Cheek the grapple for proper operation and the air fittings for lankage. Press :he DISENGAGE button to ensure that the tool.is in proper position.
19. Attach the actuating pela to the grid guide.

20. Imer the grapple until it is seated on the control rod handle and the cable is slack.

21. Press the ENGAGE button to grapple the control rod handia.
22. Manually attempt to raise the control rod to ensure that it has been grappled.

23. Slowly raios the control red to the full-up position of the hoist.

24. Nove the refueling platform above the reactor vessel and P

position the centesi rod over the positica in the vessel where it is to be installed. 5 25. Slowly lauer the control rod through the top grid and into the guide tube until it is seated on the drive or is back-seated and the hoist cable is slack. Itoper orientation of conttrol blade will be provided by the grid guide.

26. Press the DIRENGAGE button to release the control rod.
27. Manually attempt to raise the grapple to ensure that the control rod has been re19ased.
28. Esise the grapple up through the top grid and to the full-up position of the hoist.

THIS Ct3dPLETES THE INSTALLATION OF THE ColfrROL ROD INTO THE RIACTOR. THE REST OF THE CELL MAY BE REASSEMBLED PER PROCEDURE S.14.6. r 6 _ TESTING:

1. Perform a friotion test on each of the newly instilled control reds

J.3mM4 C.P.C. No. S 14. 7 f. WORK PLAN CHECK LIST P8P I of Procedure or projectPeachBottasa Unit III Preiset No. PBS-761 Work Plan No. S.14 7 k.I Prepared by/dete J. R. Salisbury 1-12-76 Production W by/h a-1 /- /8-2C 57I - /~d *2/ OA approved by/dets 7 /( Customer approved by/date t-V b OC Procedure or Special Process Refer en Compliance Seq Operation Examination or Test instruction & or Joint Process Completed Verification k Won Coned h DV & Does By Date 1 "#E Q.C. to monitor work and JPCS O thrt assure proper records are No._to Total kept. ps,,og, ~ 10 SPCS O NAE Q.C. to monitor work and gg thru assure proper records are kept, Total 17 per seg. 18 Q.C. to monitor work'and JPCS O thru assure proper records are kept. No._to Total 28 per seg. i ~ ~ SPCS O NA O .FCS O No to Total per seq. SPCS O NA O .FCS O No._ to Total per seq. GEN ER AL $ ELECTRIC ~

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