ML22238A086

NNRC-2022-000208 - Resp 1 - Final, Ninth Quarterly Report SEFOR Partial Scram Compressed

ML22238A086
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Issue date:	08/24/2022
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ML22238A081	List: ML22238A082 ML22238A084 ML22238A085 ML22238A086 ML22238A087 ML22238A088
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• I : ~- *.

NINTH QUARTERLY PLANT OPERATION REPORT HAY 1, 1971 THRU JULY 31, 1971

SOUTMST EXPERIIEHTAL FA.ST OXIDE REACTOR

9300240~21 930310 PDR FOlA HOOR"AN93-84 PDR 11/1

~WEST EX~ERtHth1'A~- FAST OXIDE REACTOR

Nlt.iH QU.UTERLY

PLANT OPtAATJON IEPOllT

Prepared by: R, V, Hyers W, P, Kunkel C, E, Russell

Approved by : J/t) ~

~ ~ Arterburn MAMger 1 SEFOl Facility

PreparP.d for transmittal to the Dtvislon of Reactor Licensing, United States Atoatc Energy Cocnmission1 as required by License DR-lS.

HF.!Dtl 1\\U.CTOl OEP~ntENI' GENERAL ELECTRIC COMPANY SUNMYYALE, CALIFOkNTA 94086 illlf. OF CONTENTS

A, Int r,1duc t ion

R. S111t.t:1,tr~ of r1 ant Oper.1t lons l, Operatin~ Data \\

2. Plant Shutdowns I

3. Reactor Scrams l

~. Cover Gas Acttvttv

~. Major Items of Plant Maintenance* lnslrur:~ntat ion 2 anJ Control Work

~. Survelllance Ttstlni 2

7. RAdiatlon M~nftorin~ Pro~r4m 4

~. Off **Site llAdioa<:tivity Release and Shipl!lents r,

Q, St~ntftcant Modt(fcAttons Approved by the Facility 8 Kan,IRH and Co~pletcd DurlnJ Report 'Ptr loci

c. Other Reportahle ltemt 13

1. Safety Systc~ Relay Malfunctions 13

2. Claddln1 Teff\\Peratures for the FRr.n Poison Rod 14

). R~actor Hearl Bolt Surveillance 14

4. Primary CrAtn Tank Ventin~ System Malfunction lfi 5, Nitro1ten !\\lower Control Switch Malfunction 17

6. Reactor Sodium Temperature ChanRe Rate, 18

7. Sodium Tenperatures for Fuel Surveillance 18 Ai Hain Primary Pump Power Sup~lv Malfunction 18

9. Instrument Nilro~en Supply Unes t o VBlvea in 20

~lt r "~cn ?.one

o. Safetv Review and Audit Activttfes 21

Tablet - Reactor ScTa~s n

Oef{n{t tons 23

, ~1~7H QL'Ail [RL\\'

F.J~~q __ (?ff:RAT I 0~ _Rl:PORT

This r~port 1s suhnlttC!J ln fulfll)rr.('nt of the requ i rllJ'lcnts of l.iccnse DR*lS for the report rcrt0d or ~lay l, 1971 thru July 31, 1971.

ll. Sumt11il_!1_. of rt.mt ~er.1t loqs

These datd are tht> result or rcai:tl,r opuat il' '* for the period of May l, 1971 thru July 31, l971.

R~actor Critical J 50, 0 hours0 days <br />0 hours <br />0 weeks <br />0 months <br /> l1aximu1n Power Level 20,0 MW Longest Continuous Run to Date (December 27, 1970, thru January 3, 1971)153. S hours

The reactor was shutdown on June 1,, 1971 to p~rfor~ the Annual Contail'll!lent Leak Teat and to acccnpli,h ~~dific&tiont to the reactor outer head seal and the Refueling Cell crane syste111,

The inert ctlls were purRed to nitrogen and argon on July 29, J971.

At the end of the rcp0rt reriod, the Refueling C~ll argon purity w*s b~ing a,hteved to terminate the outage on August 1, 1971.

), Reactor Scram~ J§ee Tabl~

Equipment 7 Personnel 1 Manual ll*

Other (Loss of Site Power) l Tot,11 20

The Cover G~s Monitor was in ~erv ice Juring the quarter, and indicated n~ anomAlous (iosfon gas activity,

Ten caver RIS samrles were obtained between Hav 6 ~nd Mav R:

six tn June, and one in July** to Quantftativelv ~easure t~e isotopic constituents. These samples consisted of routine monthly cover yas an~lyscs, s~ecial experiments to further refine samr,lln'? and fclf'ntHfcation techniques, a nrl pre and rnst-~f.D transient umples. ~o slitnificant tncreas<: ll'\\ the concentration of the flsslon products ln the cover 9.as was ohservrd.

PrcllAtnarv examination of these ~ata indicate tood c~,r~ln t ion with other cover IA8 samples obtained since Decc1i\\l-ier, 1Q70,

' All ilivenplanned as rat t of Test Pro1ua111.

• • The reactor was shut dowr: durln~ the entire :nonth of Julv for maint-.-n Ance,

A total c;, i 196 malfunct.i o ns WNt' corrt*.:ted, J!strlliut~d ai; follO\\rtr :

ff.'Ch.,ntc.il 58 t:lectric*l 60 I 11st rur:icntat fon 78

~ignlfi~ant rnalfuncti~ns incluJcJ:

Reactor Suildtng Pressure ~ontroller Reflector 19 Urptr Limtt Switch Poslttoner Hotor Control CircJtt & Rt:>d\\.!c tor HG Set 18

• Reverse Power Rcl~y Sera~ Solenoid 7A posftfon sVilch 480 Volt ~oad tenter 28 SRM 12 Safety System Relays Upper Li0lt Circuit 16 Reflector Hain rrir.iary P:imr Control Circuit WRM's 1, 2, & 3 Electromet~r 2.4 KV Bus UndervoJtage Relay 227-C Argon High Vcloctty Check Valve Argon Compres1or Breathing Air compreasor Freon Units 811S, 81l9 Cont a i nftlent l.cl\\ka MC Set lA-DC f:lcdter :lelay

a. ComplJanc~ testing was conducted tu accordance with the Technical Spf' c ificatio>ns using LTP'l' (License Tut Proctdures).

• ,,*eekly Tests 223

,U-Wt>ekly T~sts 10 Honthly Tests 4)

Quarterly Tests 4 4 Sezti-Annual Test s.s AnnuJJ. Tests 4 i or t1 l 329

b. Maintenance Calibrntion Testing was conducted in 3cr.o::-,\\ance with T~chni ca l Spec1f1catlons.

Honthl)' Calibrations s Senf-Annual Calibrations 16 Annu'11 2 Total 23

- 2-

c. T;ic,rnnual,.> ntJil'\\!H.:nt lc.1i ; test w,1:,; pc-d,*r11u:-,l Jurin~ tlw

\\J('eks of June 14 anJ.11:ne 21, J'J71. flh' rt>fudfn >! i-,,Jl WlS subscq11ently l'lcJdif tcJ, as Jls..:usst ' J lo lt~m 9,t of this rrport 1 and inner CNH,tinri<>nt l"°i\\ks l.'<'re h,.:.ucJ.rnd rt.'r,1tr,*d,

The lnnc!' <<:<*ntJin.~t?nt J..:-.1:.. test '-',IS th,*n r,*pc.1tcJ Jilrin~

thti week \\1{ July 19, 1971, to iltm 11 nstr,1tt> t:1<* int~i'.rlty

,1f the rdul'ling cell m,*Jiiicationi1. Th,* r,,,.ults £,,r h,Hh l~ak tests arc pris~ntcJ hcl~u:

Al h,w.'\\b l c 'l~sur£._J l.c.1k.~e. ~att-~. '1. /n~-

Leakage. }'./i)~*- lu_rtc..LJ..?}... L }_uJ.y.L _L9!..!._ _ _ _

1 Mer C,.int.1l11nent 16.S 9.00 + O.J9 4,4 0, 39 Outer ContaiMent l.4 1), 2) + 0,1) o:ot !1casurt*J)

d, Sa111ples of tht> soJium for the St:fOR rrJm.1ry lo\\Jr,,crc obtalncJ Jur.~ 16 1 1911. One siet of s,1mples was r~t.ilnc>J on sttc for radiochemical annly,is. *. The other 'let,,£ l-!umple curs were sent to V.illecitos Nuclear Labor.,tory, l>'here the)* were analyzeJ for metalllc 1Jtlr,ur1t1es :1s well ;is radiochmll:ally.

These r~sults ar~ surimari?.el! be! ow. An increase ln the j\\umi nuM concentration was noted, ~nd an 4nalys1s or a scconJ s~mpl~

ie in progress to cutroborate these re~ults.

Metallic Constituents of SEFOR So<llum in

-Saiiple..J)~t_!,_ine__d.J_~ne l_h Tiff ____ --

I l em.£El Conc.e:nrat lon.~l Al 100 Ca, Co, Hg 6 Cr, Fe '

AR, S1 2 Mn O. b r.. 100 Sb, ~b.: 30

(s' Li < 10 Ra < ~

Sn, Cu,: )

Pb, Nt I Ti, Zn., 1 Mo, V < 0.)

Be, 81 < 0.1

< Represents lower 1 im 1 t of det~cttun for instrument used.

1hc L,Uhl,n* CltOUnt *.,',IS 2} ppri, wh *.1-., the u-2n W,IS O.! p(ih

.tn*l tltc* U-238 w.1-s 5 Jlph,

4,4 X 10 4

!ib-124 <4 x 10 3

,1. r.nv 1 ron.':11'.'n r,1 l S,l!'lp ling (May '. 1971 thfl"'Ugh July JI

• 1971)

Numl;er of \\'t' gctal 10n S.1mJllc~ A11al)*ze,1 15

~umhttr (If So 1 L S.lffl(> I '?S l\\n;t \\ yzc.J 6

-iumber of w.aer Samples Analyzed 8

~ -~~- -__ B_e_t_'!_ __

Hay <lS 1108

.June < lS 11 S 1 July <lS 917

Rechr.c'K l.evel 50 1820 Pre-Operational Avg. 13 987

NC' evidence of Co-60, l-lll, or Na-74 1,as observed in the vegetation s.-imples before transmittal from the sfte,

2) Results of Soil Ana l,tses

~.I)!!! - --~~--- Beta

Hay 24.) lS June 22 27 Jul~* 2.l 22

Recheck Le ve> l 32 4S rre-Operat ional Avg..25 34

No evidence o{ Co-60 or Cs-\\17 was obser~ed above detectlon llmlts.

)) R~*su_1ti_uf_ 1*.'* *,lll*r,\\11,llysc*r._

\\fo nth. _ _ Aljl}l.1 __ - l\\cLJ *--------

~!.l y

• 1 )i 10 **8 ) X 10-S

.Jun e r. l X 10*6 8 ) X 10*8 July '- l X 10*4. 6 X 10-8 Re ( he~k Level ) X 10*6 1.. 10- 1

• J X Pre-OpcraL Iona) Avg, <2 X 10-9 6.1 x 10- 8

So Co-60 or t.:s-137 were "burved.ibove detection tl111its.

b. t~nVl}:£.. nmental _Fi_lm Nonlturi,~t...(May l..._ 1971 thru _ Julv 31_._ 19711

Sumb e r of Slations 17 Total Films AnJlyzed Sl

?taxlcr. um Rad lat ion Ll'Yf?l Reported 16 mllliraJ/qu~rter*

Maxi~um Radiation Level R~portcd 8 millJrad/month Jurtng Pr<-- Opcrat1onal Survey

c. Personnel _:~ltor~

1) Numbe ~ of film oadges issued:

!1dy 48 June 69 July 79

2) PE'rs.:>nnel !-faximum Whole Body Radiation 430 mra Re~eived (Quarter ending June 30 1 1970)**

J) Personnel Maxlmur.i \\..'hole Body Radiatic,n 2:S0 mrcn RQccived during Jul y, 1971

4) N11mbt)r of Ex po s ures to Rad 1oact lvi ty No ne Conccntrat ions in At r in Excess of thnt specified in 10 CFR 20

5) NUJ!i ',, r of Radiological Spilis or Con-One-'U t.1.'ll.1..1.1.ton lnc ideats

-.-The report for... J°uf;; f9n, s h owed 16 mllltrad at 1 station. However, the c o ntrol badge showed 4 mH lirad, i :;,ficat t.ng possible t.rradii\\t ion of lhc film in t rnnsit or stora,t, (The reactor w.,.* -;!1ut down during the entire month of July. )

• • Reported on a Calendar Quarterly basis for April, Hay, and June, aa per 10 CFR 20 1 Section 20.39 (ii),

'""' Result of irradiating the tei:iperature sensitive paints for the FRO> poison rod.

Necessitated minor refueling cell cleanup.

l) Ftssfon _ and Act:)vatl o 11 ProJucu _J.!_xc4'~t t _r(!tu11)

ol) x 10

• r~.\\t;tl curie,1ctl\\*lty rtlease,t (CO ' }. } *6,

b) Total voli.Jffl(' o( liquid waste Jlschar,ed I. IS IC I Q-i (g.1 l tons) c) Tot.11 Y'-' lu111e or Jflutton w.iur (11a 111.ln& 5.0 X 104 d) Volu~e averJge ~oncentration ~t discharge 'l.9 x 10-t po 1 nt -~l x 264 (1.1rt/*t)

( 1

• C) 10*5 c) Ml'C usvd *{~C 1/mO ),/) X C) Pcrc~nt of 1 fmll (~).: 0. 06 to-'

g) H,1xlmum cvnceutration releaa~d. neragl'd ),0 X over not more than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> (uCi/at)

2) IrJ.t)ull?

a) Tota I cur le uct i*d t~ rel c,,sed (CO 4,4 :c 10- 2 b) Volume av~rage concentr~tion at dis 2.3 ~ 10-,

charge point:.l2..!-!l X 264 (1.1Ci/81l)

(t

• C) c) Pt'rcer.- or 11ml t U) 7.7

3) Est im,H~ Carbon 14 -~as~ij_ 4 X 10-J

Note: All 11quid8 are released ti) a tlle held. HEar.ured con centrations refer to values at the point of ditcharge into the t Ile field.

1) Noble and Activation

a) Total curie activity released (~i) 6, 38 X 10-)

b) Total *10J11111e of g.is released (ft3) l

• 27 x 10)

C) Time average release rate ~.1. at (µCi/eec) 0. 8\\ X to*)

d) ~PC used ( 1,.1C1/m£)* 1 2 x 10* 7.9 ~

e) Licen~ed limit tor annual ~verage (uCi/sec) 800

() Percent of annual limit (%) 1 x in-4 g) Maximum hourly average uleau rate (1,.1CJisec) 5,1,c 10*2 h) Licensed limit for hourly averag* (uCl/sec) 1400 i) Percent of hourly liM1t (~) 1. 5 x 10-l

• Na-22 identified as gamDa emitter.

~* Based on Kr-87 observed ln ~over gas.

.!) 11.1),,i._;cn:. Wllh !1,11f*li\\\\. ' i :>!J-J.J)':i.1nJ 1*,1~u-*ul.1lcs \\Jlth h,1 l f -11 v,*s *, ti-J.1ys.

a) l'lH,\\l curie ;icLivit\\' re:h>aJe\\l (Cl) ').6 >< 10-R t,) rtn,*.1v,,r.-,;1t! r('lc,Ha* rnt~ \\J.!_'l-*.:11 (., Cl/st*,;)

• t,. Ii,- hl*'}

7.~

') HI'(' us,*d (;.ti/Pl:) I x 10-IO d) l.lr~ns~d limit for annual.1\\'t' L'Ji,t (vCl/st>c) 5,b x 10*)

C') Pc.-rc,*nl,,t Hmll <'->, l x lu -4

{) ~axi~u~ hourly ave1.1ge r~lc~,e rote (~Cl/s~c) *9.~ x 10- 7 r,) l.h:~r.sed l l111lt for hourly averap,~ (11C 1./!lei:) 5.6 x 10-2 h) P~rccnl of hourly llmlt (%),1, 7 x 10*3

l.l~uiJ 18 c;.1 sc,~us 9

f.lqu IJ lo Gascou& 9

!~'!.!'..ill.tl'.. Su"llla r..)' of J-*.ad ioac t ive ShJP.*e.!.t!_

~.!1.L.L.. lfil~_lj 1.!)'...1!.L_197 ). Radloactfv,

7/7/71 Approximately W gm Na GE (Vallecitot)

(Prf~3rlly Na-22)

---

~ *BaseJ oo the posaibl~ prc>s~ncc of l*lll. - --- ----

9. Si~nU lc.olEt _!!l)J Ii (C,H Ions~ Aj'j)f0\\'1'J.. bj_ f.1_* t.J.l.!..Y. ~.1.--*r.rnJ

£~m~t**.:."il1-!!..!.r:1~. _P_cjl.!'_r_l;_ f1:_rJ~~~!..

th__. f\\lfi(' tn th<> l ow ~,,cilum l cv1*l !iWtlcti t>rtdj!l' drcuit

\\ilas u.-Jn, *:1t<'*f, !Ii<' that "t hl<,wn (1111~ wfll r:iuse., t~*1H; c-t

,,0\\11'r to t,,,rli l<'P.!I of tl11* hrfd~'-' drc11ft r :tther tl 1Jn ro tust f>nt> IC'P.. fhlR rr,wt,Jei; 11dded.,ss11r,1nce cf t!etNt lnP.

~nv A~1run~tfon ~, thf hrld~r circuit, hv CAu~lnr n tr1~

-.hn,1I to l,c, *11r in th(* c*vr*nt,,r A fuse fcill~rf',

The haH-ton gr..lppl1.: WJs r10JH led by th.-,1JJttlon of two t*lescl>ping 11prlngs bel\\,:,:cn the tr.ipple body and the c.~ble

.lltaclvr.~ nt, As ti,c gr,,pplt is lo\\o*ered and a roJ becont's fully insert c.*d, tht> springs,,re co111pt<:ssed by a 100 lb welghr.ibo\\.'e th(Ofll which P'-'ffllcs th:1e for coai.tdown to occur wlthcut creating a slack cable, Wl,cn handllng fut-1 with the h,1lf-ton gr,1pplc, the 100 lb welght 15 attacheJ to the grar-r,te to permlt se.Hing the lightener rods, Prior to modJfic~tion, lnoertlon o( a tight~ner rod cau~ed the load to Jrop off and the low load l111lt to shut l.lU the hotst, Lut co,tsldown crc,1ted a slick.'.:able.

• The slack

,-,ble r,ermitted the graprle ~nd weight to fall to oric ~ldt cr,...at Ing the potent ta I for bending the rod,

A sof~ty systeni jumper panel w~e inst al led in the Control Rolim to <'limi11,1tt> the,isc.> of,11 ltgator clip wire le<1d jumpers.1nd th<-.ittt:-ndant p"ttnttal for shortfor, between t~rm i na ls or impn,per l<>tT.1 l nJ l s,* l ect iDn. The new panel uses a jack plug to create~ clr~ult to jump~r a sclecteJ f un ction, Th~ nc~ jumper d evtcc5 Are controlled In the s.al'lc m.1nner as th~ wire jumpers, by stor:\\ge in a 1oc~ed cahi 11et,,.i th each use entered tn a ju111per log,

d. l1an Acc~ss s,Jit rlowrncter

A flm,;meter equipped witla a high and low flol.' switch..,.as installed in the Man Acct"ss afr supply line. The Jow flow trip closes the shut-off valve for the vacuum exhaust sy s t e~

by means of a lhre~-way solcn~id whlch vents the pre*sure

!rum th~ dJ.tphragm ot the sl-iut-~H valve. Electrical power to the ~olenoid v~lve ls aupplled thru a ralr of normally

Opt1n CllOl,lCl~ ~hit:h,HC' c4clU,ll(',l by th<' 101,1 flow lrlr, Loss of <' l~ct. r h:,, l puwcr ul:1!\\ n,, t c,rnsc the vacuur.-.

uhaust sh1ir-~,ff valvt.' to d,ls~. An,JuJlblc.1 Ltrm i&

.ictu :1tt-J by t-ltlic-r the l.1\\o' flt,w ~lr.i hi!lh fll.l\\J switch.

A m.rnu.11 lo!lC'bc *1alv~ w.u, inst..il l~d (1n thl' out let uf th<

f lnwcter ll' H*;.ul,Hc fl,,1.* tt.ru the meter.

The ~e,H p.tck,1v,~ I,H tiie Pl1111p-Around-ru111p volt-pac wu ffll'J l fled to Hqu tr~ 60 seconJf for ch.lng ln~ th\\?

\\'oltage from zero to full voltage, Prevlousl~ the time requlreJ wds 30 seconds. For reactor o,eratto~,

the flow fs llmfted to l 8i)r.l to provide grNUr unsl tivtty (or detect ton should a >>nall leak occur in th~

rrll'll8ry coolant sy~tem, Due to the low puMr voltaRe anrl pump he,1d r~qu{red to maintain chi* rlow rate, sysu111 chanae1 whJch affect bu~ voltaRe or cover R*s pres1ure cause th~ p~r ftround pUfllp flow rttt to drift, Th* flow rat* ~ust then he r~turned to an acceptabl~ v,Jue hy mak ln,t small corn*ctlons to the pl.llDp voll*jU!, This modfflca tlon s1ows the response of the volt-pac control lliYl-Um to irprove the abll t t, to ~ake small correctf~ns In the a~plttd pump vnlta~e.

(. ££r~l_l~lector _Systf!ffi Calfbrator Circuit Sh!!.!dl.!!&,

The 1o~rce of 60 cycle noise in the stgn~ls from the cables in the c~llbrator circuits. Shielded cables were tran1ient flaslon chambers was created by unshielded

Installed to eli~tnate the noise.

A circuit h~s been provided to ~~re 4ccur3tely measure the ExcurBlon Mode Time Delay, A set of spare contacts on the FRED fire Switch and spare contacts on the relays in the scr~m chnsses were used to provide a 61gnal to a scaler timer to give ~ore accurate m~asurement capability of the Exc*1rsion Mode Time Delay. The clrcui.t does not affect the normal fur.ction of the Safety System.

h. Rt-actor Vessel l1ead Seal B_acb~f

,\\ seal was installed between the reactor vessel outer he.id and the vessel support skirt to provide a cover gas backup seal. ~,en the primary cc-olar.t ter:iperature ls increased, t:,e ruultin& rot.>tion of the reactor vessel flange temporarily reduces th~ tet'slon ln the outer head bolu. (See item 7, page 19, of the Eighth Quarterly Plant Operation Report.) In some instances~ thifil may <'8USf' cover 8-"9 lt;'lk.>ge to <'<"Cur, *rh<'

backup s~al waa lnstalI~d to reduce this le~kage to a negliglbl~

11111ount.

r\\,)ll0wlnk t:h' 'l1H,t.1llJl h*11 1 tests wi,Ht' r*1ri(,rn, *d,H r.1tc>,I pr<<*ss\\trt* ll,) Vt*rlfy t.lw '-~**.:th*,*1h*ss \\ 1 i t'H.' i,;c.,\\.,\\ !'>., r-*n

,if th(' sc*,11 i11st.il l.u fon,., sc.11,: 1~1np 11.1s.iddt-'1 unJL *r,i,._,

n,1t anJ t.',lsh<-r,,n 1.*.ii:h vutt'r 1i.. *.1J stuJ, In Nd,*r l" pr,*v1J,:

.1tl,*l{u.1te lhrt:';1J,~ni.i~t:r;t *nt ~)f 111.,, stud t.*11sl<'111,*r pu11..,1* l*,lt s c.1 c.kt?t on lht* outer h<*,11\\ stuJs, th~ tNisllln,*r ::iupp,,~*t h.1rr, *l w,1s shortcnc*J by,1ne l111*h,

t. ~efoe 1J~cJ_l.. C l~~n.!__B.:1..~'-rA(!_~c)' _ _.~~.!_rJ.. ~.. ~aJ ** ~.>'!>~~

lhe Refu<'l inJ.' Cc l l.ind the Rduel ing Cell CrJne have been

~edified to p~rmit recovery sh~ulJ a ~Alfunction o! one or more o! th~ comp"ncnts occur, The m~~lflcatlon lnvulveJ:

1) cJrHllng enc holt? fn the north wall of the Rduelini,;

Cell for trolley retrtcvnl,

2) dri 11 lng t',,ur holes in the w,~st wal 1 Clf the Refu~l it1R Cell for bridge rctrlevRl.

)) il\\St.111,H !on of the brtdr,<? r~trlcval syst~tn,

4) inst,1llJ~ lon of pans to pnrntt trolley retrit'\\'al,

S) ch,ngcs In the 'i tlJn and 10 ton Jo,1J blocks to permit att,Hhment of auxili.Jry hoist cables,

6} changes in the 11 ton grapple weight.

7) changes In the r~actor vessel head lifting flxture to permit manual lowering or raising of the head,

Following the l'lodlficatton, the opt-rabillty of th<: crane sy~tem was demonstrated. A test was performed to d~monstrate the abilttr to :.,ove thl, bridge and troller using the aner gency retrlev;il syster.i, lhc inner c.:,ntalnrr.cnl l~ak test w.1s repeated to d.. -~unstrate the integrity of the w£:lds,1nd the nt.'\\ol p~netr.Hit.>ns,,Jdt*J,1s a p,1rt of the cr.'.lnc e.mtc-r~~ncy retrieval modtftr *. ior.. Some vC1lt-p:tcs and conJuit runs wen relocated to pr,wldc room f1.>r the refueling cell pt*nC'trntlons ad.-ted as part 0f the fTIOdiftc.itions.

j. FRF.D Positfoner l01,*cr l.frnit Block

Th~ reacttvlty lnsertlon lnf~rred fr~~ the ~~~sured tr~nslcnt flux Jata during the famtli:ullatlon transients was,1bo\\!t 4 %

greater than that determined f rOfll ml!a!'lu:'L'ftlent, of tlie poison slug reactivity worth during static test:J, A l,wcr l Sr.tit block (shim) vas installed,,n th~ FIU:D positlon4!r to limit Jts tnvel w!aen *.he polson slug Y.1s lowcnd into th1.: core. Hlth the shim installed, the m.1ximun static vorth of the sub-r,ror.ipl poison 11lug was limileJ to 0.94$, which would corrcsponJ to,:1 dyna111lc worth of 0.98$.

• J.0-A 4 inch sch~*.lule 40 stainleu steel pipe, 11 feet in length '""' inserted into the Cov~r Gae l'1onilor loop ln-s1de the ~cfu~lln~ Cdl nl'ar the potut at whkh thl' hhlp pent:tr.:1tcs the w,111. Th<' riJJitional loop vol11nU1 fs Jc>slgiwd tCl rt-Juce the Cover Cas l'lonltor b.1ckground,ign.11 created by the pres~nce of Ne 23,,ln acttv.ittvn proJuct (half llh 38 ~ci.:on.Js) pr..,J1H"cJ by an n, p reaction un s.i23. This addttlo11al volur:,c of 1 ft3 proviJcs,1 Jel.1y o( approximately 2~ minutes (or nearly four Nc23 half livt~) at a flo~ rato of 0,4 ft3 per minut~.

The Wtdr Rlnge ~onttor circuitry was nodifit>J to lt~lt the input current to encl, WRM to approx lrnntely J, 2 1111 l l l amperes, vht c h is l~u th :1n the aatur,Hton value of the Input electro111eter tube, lJ ut about thrt~ tlnles tht> v11~ue at 20 Nloit.

During the sub*prJmpt transient ($0.9) from S MW) on Hay

't,, 197\\, the perik power attained wu about 11~ ffl'. WIU't No, 1 and No. 2 ou,r,.it signals wt?re conn~cted to the Oat11 Acquisition System. The signal fro= WR.~ No. l reached saturation and then

• 1rned abruptly downscale. Subsequt!nt test* indicated a zero shift had occCJrrcJ and the WM h.1d berome less stable. ~aasurements were performed to detemine the input currents at which each w'RM saturated. Since ~he input ~urren,. s to \\..'RM No, 2 anJ No. ) reached &,Huration values during the me.isuresnenu, zero dr Ht and 10111e 1n-ata~i l lty were observed on these two instruments. Att*pt*

to oper~c ~he reactor ln steady state conditl~ns subsequently were interrupted by spurious high flUlt scrams which occurred Jurlng ct,anglng of the range st!lcctor switch. The scrams were caused by fn~t~hlc electr~meter pairs in t~e pico am:ncte.r aodulc of amplifier No, l in the WRH circuitry.

The elcctror.: c> tt?r pairs were replaced.1nd the '-'RM stabll Hy was rc,t,ircci. lht* curtt*nt limiting circuit installed vas designed to prcv er.t dam.1g<' lt> th(! 1:~w electromf:ter p.>irs.

The current limiting circuit involved the addition~, *wo dlndes (1SJS7S) in par~llel, but v1Lh oppogite directions of current flow, ! n st:r ies with.l set of contacts on the Kl re lay and conn<*c: t.:*J bct1,,cen the l..'R.'t input and tht! cOl!IITIC-'I (ground), The ~urrcnt limiting circuit was in~t11lled on&J in the previously unusetl uppermost range of the WR.\\f which ls.\\bovt-the O to 1 is,: of power r.1nge. The resistor-capac ltor feedback network which existed in this range (Rl

,1nd Cl 5) was r-.ffloved. When lh'"' ~RM range selector switch w,211 placed !n this po!lltion (identified as "O-lHX Excursion),

tla* rl'i. lst..,r-1. *.ir,,1.: it,, r f,*,*,llud: rwti..*1.*rk ~,1 Lht> O* l i'>~ rJnP,,1 1o*,1s usecJ, the c ~H\\flt:<' C i-n, he-int l'l,\\Jc bN,.cen the lloh.' r,lng1.'

1i--,;itions by a dt0Jc- (1~9141, On!~ - tn thl,; pcs1th1n w.u rt*l.1y -~1 '-'TH'q ; J,.._,lf t -.*,*.1n1a*n the currrnt li:nlL(nij dr,*1dt

!nt~ tlw i11\\u1t,*Lr.:ait.._,, t\\\\\\\\ ~R."t. Thus, i,,r all !Hf',t.1~*

st,\\tt> optH,Hion, th" curr~*1t 11Miling ctr.ult '-'M, n,, t

(: \\)I\\Ot', t t>d.

!h,n\\'.h t('st..,ii thl' current liniting circuit wtth input curr... nrs up to 10 l'lillf*,1111pt\\ lnJkatt>J propt:- funrtfor.ing nf th.:- circuit, The max1r.,ur; c11rr..-nt that un be pr\\.l,1uccJ h** thl' n1:11(rnn <ll*te.--tor for the "'RM is appr-.>xiriately 8 m1lli-.1mps (<lt>tc-mlnl'<l t-y t!1e hlp.h v,ilt..tgt* pl.)Wrr supply),

C11rr('1:t leak.ii,

• tlu**, the,.ho,le ls or tl1c* order or 11.,-7 rn,1

<.ib,1ut to*!. ;; i,,,*.. :n), wld.:h,dll h,Wl' a fl('f,)(l(fh)e t>f(t?ct

<'II the,:1~ut slgr..11 Jurin*: ~*11t.*r,H ion In the po..-er ranges

~,r dJr Ing ti :,:,, :-:in~ i~nts.

A "Y" W.\\9 fnstal1'J 011 tl,e ~.1~ Rub::,l~r Inlet line to allow d~.intng th,~ ll'lct pip.-. lhf! pr,,s~ure Jrop through tlie ~a> :

Bubbler had ln~rC'ascd 011C'r the past few mon,h11 bec~t11se of oxl.::t' depositH In the inlet pipe, The cl~.1nlm1 vhl.:h wae performed foll.:*wtng lhe "Y" inRtallatlon rrsulted In a rl' ductfon in the pressure drop across the bubbler.

l~ad shnt hnd been rlaced around th~ fission cha~hers to reduce the ~afl'ltn~ J~~~ rate on the chamb~r. The use or l~ad shfeldln~ created a softer neutron spectru~ at the d~te~tor a:,d a J;u~e numher of lower PnPTf!V ~affl.1Ms, ll<'th effects contrH,11t~d t.o.1 hl1her h.1d,~round curr~nt. The softer n*!u trnn spectrum caJfied a hl~h~r captu:e to fission ratio, and hrnrr ~nre hnr~~r0und from the decay cf ~-2)9. The low enl'r1tv ~.111vM rad lat ion cC'ntrJh11terl l!IMe heavfly t-> tht' photo el~ctric efrect th~n the h1P.h ~ncr~y ~Jmtn~s. RtplAc~r.ent of th<> leAd hy s,.c r~d11.::<'d th#' ~apture to flsf.lon ratio hy liard'-'nln~ the ntt11lron ~.1<>.:t ru1...

lhe poi1f(Joner drive mvt,,r.1r:d iear H<1Jctor "'"re 111odHlt>d !i:'

t?i.,t a l'!'.an fn a man acr.ci;s ~uft can Install the unit and make proper a1f~nment ~1th the drtv~ shaf: on the posittoner. The olteratidn& provJde vertical, lateral and rot~tfonal adjust*

ment on the mounttn~ h~$e, The ~reaAe that was formerly used fn chc r~ductor gc~r bor. was re~laced with atandard oil (NRRO-R$ SSU at 21n°) to eliminate ~ear tooth wtar which had required pre111a ture rep hcement of the reductor,tear. An "o" rfn~ seal was added on the lower part of the kear box at one o( the shaft be~rlnR~*

J)uring the pcrforr.i.1nc.:* ~)r the Surv,~i llancc Teal Ll:P ?1-_Q,-9

":Ofonlhl)' Ch.1nnel lt.'~t t*f th~ Rea~lvr S,1(ety SySlelll Autornat tr.

Trip **unctions" on ~1.,:,, 2), 1971, the high Oux trip for WR'I s~,. ) did not c:1,1iH. *,1 scr.11:1 wht'n the t~st toggle switch was

.1ctu,1tcd, Th~ switch w.11,,1.::tu,1tcJ Sl.'Veral til!les, bi.t no trip occurrt'd. The s~urct of the ~alfunctlon waj identified dS atu.:k com:.1.:ts on mercury-wetted relJ)' KJ Uutonwctc Electric C"** Seriu \\'54, P,1rt No. PM-4400-lSOA) in Chauls C of the safety s~*stan, Thes(' cont,1cts nre ln series ulth th* acra:11 contactl.lr,:oil ~Cf,lSS th\\! 12S voe supply. Contact protection drcults *had hcC'n ndJcd ln p,ual lt-1 with tl1e BCUIII contacror coil. Chassis<.: wa, runoved from the p,1nel and inspected. No (nd tcatlon of an o\\'ercurrcnt Nnd lt fon (111elteJ lnsulat ton, burned CPl:'lpont*nts, or dis'7oforufon) vas oi>served. The relay

\\l<l & r (!t.loved for i nsp(*,: t Ion a nJ wlu.-n 1t was inverted* the con tac ts opcneJ. A new !'('lay was installt"d and the surveillance t~st was co~rl~t~d with satisfactory results, The high flux trips for W~~ N~. 1 3nd ~o. 2 functioned prvperly in all tests.

Since the trlp logic l~ one*out-of -threr., high flux scram pro tection was maintained at ~11 tlm'-'6,

During thc> perfonn,rncl? of the above surveillance test, it was also found that Lh<! power supply br'-'aker for the main secondary coolant syst~~ pu~p (~SP) ~inJtng dtJ not or~n when the l~st switch for the high pua,., wf nd Ing t~perature lrip vas actuated.

The ~ource of this malfunction was td~ntt{fed as stuck contacts (mercury-wetted) on relay ~15 in Safety Chassis Rl. This pair of contacts transmits a 26.~ VDC signal through Auxiliary Trip Chass ls Z to trip the M5P supply brcakr~ *. The safety system scram trips in Ch.1ssis bl functioned properly. The contacts on the relay which mal(uncti~ncJ did not open ~hen the relay was re*

~ovrd for inspection. An<!~ rrlay was installed and surveillance tests '-' C:rC perfomcJ \\:Ith satisfa.:tory results. r.xamfn.:ltl o n of lhP components and wiring in fha~~ls Bl revealed no indicatl~n or an ovcrcurr~nt condition, Beth relays w~re replaced and satis-factory S)'St('ffl operation w.:is J,---nonstratecJ, lhe relays whi<'h mal functiont'J were returnPd to the ~anufacturer ~ith a request for

&n.inalysi!l of the cause of the malfunction, and an estimate"'

the ~xpected lifetime for mcr.:ury-~~tted relay contacts. The manufacturer attrlhut<:s th~ r<.'lay failure l~ "curren*.s or voltages in excus of ~pt>ciiie,J llr, its, thereby destroytt\\~ the protective mercury coatln,\\," Tho req:.1est {01 an estimate of an expected ltfe-t ir.t was not ans*Jertd by tht' vt-ndor, however a ttat wAs reconnended which would te~t the relays for hrfdgfn11 act ion which may be related to an individual relay lHe t-.xpectancy, The m11nufacturt-r reiterated the need ror surne form of contact protection, with a prderred contact protection being~ r~sistor-capacitor net~ork. The manufacturer's recommendatlons are under review by the SF.FOR Star{ nnd RRD F.nglneering.

The r.iaxlmum d,,JJtn~ tfflperaiure (or the f'RED poison "lu§s \\ilU orittfnally (.*$Un..ttcJ to be frr,111 l37o*r lll 1sso*r. (Rd~rtnce Suppll'ITlt>nt 19, rage 37, 38,) ~.atcrl.11 co111ratab1l1ty tests wen IIJO.lt lboo*r to dl*r.h)llStr,ltt..> the ColpJbflity o( the potsun rod to opcr,1te,1t the expectcJ tcmpt-r,Hurcs. Sub"'*quent thenoal ana.ysts of thl' f lfl.ll Jcsign Hsulted in est im.ited cladding tt>nperaturcs of up to 1760'F for lil'fflC of the planned tHt potnts, lhe inilt-ll power levels for the sub-pro11>pt critical and supu pr o mpt critical cr.1Mient tc5ts were thereCou reJuced accordhgly, so that the maximum i>!;tilll.llcd claJding te:niperature was l~liO'f.

Prior N the per(ot't11.1nce of the sub-prompt trandent tests, stc.>.1dy H,He tests l.'\\!re performed, uslng tMperature ~f'nsit lve paints appJ icJ to thr* poison rod, to fn\\*~stigatc the cl.adding temperaturrs ln the rc.1ctor. lfl)wcver

• the d,ltA obtaint?d (r011 lheae te!lta were lnconcluslv~. As,1 ruult, tht' 1naxfnum allowable lnltlal power level (or tr.1111-it*nt tests ("'lth the r-,ison rod fnsttrtl'd lnto the c<>re) "'as 1 imlte,i as Jiscus~ed abc.wt=, b,1sed on tmperatures c.11-cu)ate,J from lw.1t trans!E>r.an;ilyacs.

3. !£."!..Ctor l!caci Bl'>l t Survell lance

Corrective action8 taken to reduc~ the head bole stresses to accept~ble values lncluJe~ a reduction tn the bolt pre-load to a v Alue of 3000 psi on April \\R, 1971. The pre-load reduction required use of the stud tension*r, and during this process the strain gages and leaJs were da~aged. (These strain g*ge1 had been used to investigate bolt s:rtsse5 1 as reported on page 19, ittn 7, of the Eighth Quarterly Plant O~ratlon Report,) Reraira were c1tte1npted but subsequent dua obtained rrocn the gages proved to be unrcl table.

After the bvlt,re-lead ~as reduced, and the reactor coolant system h,d.:-xpericnced several thermal cydl!s at 10'/hr, nln<<.'

of the ~uter head b~lls were checked foT posslb]tt elongation by applying a rre-l~~d or )000 psf wtth the stud tensioner ar.d measuring tt1e nut rnt,H Ion which could be occompl ished at this prc-l~ad. lhls ~cthod ts no t very accurate. stnce a nut rotation of l/16 inch (measured on the nut O.D.) ts equivalent to a ch3nge or a boat '3600 psi in bolt stress and nut rototlon depends on the torque appl.fed br h;rnd through the stud tensior,cr apparatus.

V.ufat tens of up co S/16 of an inch had been J>Yeviously noted for mcasurm~nts on.1dj.1cent b"lls. Ncasurem~nts obtaine'1 during this ins pee lion sL.J w less var i.Jl {,.\\n wilt. five me.:1surc.t1ents ind {cal in11, zero rotation *. (See t.1blc bel(.)w,) lherefor~, considering tht accuracy of th Is mt>at-Urt';fflcnt, it vas concl uJed tnat there was no los!l In bolt pre-load Jurin~ themal tunsfencs wfth the lni ttal

r,rc-lo,1d re,lured to )non pal. The re 11lts l'lf tht ll'IU11uu*mt>l'\\U (111ade on Junt 17, 1cn;), ue atven ~elou:

~.~r _ _!to!_!!~ \\Jhtn r~~_toned to_lnnn,c*t

,_ t n 11-1 l/ lt.

l~-1 n 4-2 n 14-2 1/4

)-) 1/16 7-J c) 12-3 0 lS-3 1/4 The submittal contalotn,. infor~*tton reiardln-ProPOltd Chan,e No. S to the Terhnlc~l Specification*, dated Aprtl t8, 1911, stattd that the per(odic st1rveil lantt pTORU" would be lnl ttated prior to August 31, 19n, and th*t one of the outtr head bo\\U ex~mtncd in HAr.ch, 1971, would be re-exa*Sned betvetn the 1ub prompt and super-prompt tranttent t* t proar.... Th*** requtre mt>nU have been l\\tt or exceeded u dhcuued below,

(1) All~, the outer head bolts and all of the inner head bolts were ex*~ined ~Ith ultras~nlc te1t equtp~ent on July 16, 197\\. The ttsult* of thtte teats howed no observable defects in any of the bolta, (2) F~ur outer head bolts were rt!l!loved for visual intpec-t ion, dye penetrant checlcs I and le,tgth **1ure111enu in July, 1971. Three of these bolts had been e:umiried previously in MRtch, 1971. the vtsu~l e~a~ination and dye chec~s showed no evidenc~ of crack., wear, cor datl\\B~cd for about 1 1/2 turns on the nut end of the rosion, or Railing. The thr~ad on bolt number R)S was bolt, but this does not affect it1 1etvieeabSlity.

Bolt number D3209-13-47 was installed to replace a bolt which had sustaln~d dama-~ to several thread* due to a Mlfunctton ~f the stud tensioner.

The lenAth of the belts had not cha~.Aed, u indicated by the d~ta in the followin~ table:

aot t Old s~w l\\olt 1, en~th.it 7q*r No. Po.~_1..!_!2..1} I'".! U..1.~!J * ~..!.£.h...... 1.!LL_ }J! IV

• 1971

B'JS 14-2 s-z 24.2JS 24. ll S 89 15* 3 12-l 24. 16) 24.)62 Bl4 l!.- \\ \\ 2-1 24. lJ ~ 24. )1)

DJ209-12-2 24,4)0 13-47

• The bolts were mov~d to the new ~oRftton in July, 1971, 10 th~t they would he more accc&~ible fC1r future aurvefl tance.

4. Pr!£1ary Or~ ___ T11~U~!E.!_~ste'!l HaHuncti<'n

PrepAratt~ns for schcdul~d fuel surveillance operations required reduction of the cover ~as pressure ln the rt.actor veaaet and prl~ary dr~fn tank on Hay 8, 1Q71, Recause a iradual increase ln restrict Ion r.o f 1,; w throut.h the nonaal priauy drain tank ventfn~ lfnf had been ohserv~d durtn~ prevfoua use of this systel!l, a dedgto~ to use the tl!letAency v.ntlni syltni at a control 1eJ flo'"' rate wu f,i,lde. The drain tank pressure was satl~factor1ly tcduccd by th1s ~ethod, but the reaulta fndlcat ed that th~ e~erkency system wfts also parti a lly restricted.

The et1:erj1ency drai n tank venttn~ aystea provide, A backup to the shut-off valve in the pun1p around 1oop line, by autoraattcal ly de-pressurtiin~ the drain ta nk if a pr!Nry coolant syatem f~il ure were to ~ause a reduction lo reactor vessel cover **s pres sure. Thfs ha ckup function provides addt!d assurance that a sufficient am~unt of res erve sodium will be avatlahle to cool the core follo~tnp such a fatlure.

Since the av"1 lab le inforlTlilt ion indicate<! that

• r.trnit Ing Condi tion for Operation (tCO) could not be mtt,,,.actor-operation vas not resumed unt iJ tt1e c,1use of the m.aUunct !on could bP. (nvf!&t i gated and corrective action could be taken,

lnl~lal Inspection of the control valves. l ocated within the nftro~en atmosphere of the fnner contaln~ent, did not reveal cause a flov restriction tn the nonnal vent system valve due the cause of the ~alfunction, although a subsequent test did

to condensation of sodium vapor, The nitro~en atmosphere was then chan~ed to air and inspections of the system tndtcated that sodiuai or sodium oxide, deposited on the check valve between the vent line and the gaseous radw4ste header. had apparently caused the check valve to restrict the flow, The

- 16-valve w.1s cl eJncd, th~ syfi teri "'.ls ret Jrnt?J tl' s<.>rv ite, anJ normill op<'r.1t ion w<1s J"rn,mst r,ited by stanJard surv<'il lane,'

tt>!it procedures, Tia* r.1t<' o{ i low lo Lht normal vent l fn,e had been contr~llcd by p a rtially thr o ttling a valve Jn the line. Rt'strf c th.*-:. to flow In the nor111.1l vent systen h,1d occurred e,1rlter due to sodtur.i condensation in the throttled va l ve, To el lmin.ite this problfS!l i short length of 1J - inch tubing was installed ln the nMnal vent section of the syHer.1 to provide the r<'41ulrcd flow control "11th the r.ianunl shu~-o((

valve in the full open position. A ptrformance criterion hJs bern defineJ for n l, rmal operation of the 11ystem, to assurt' eilrly detection or any future m~lfunctlons o{ this nature.

The check valve w.1s rc-tn.'JpecteJ on June 26, 1971, following the annu:11 cont a lnrncnt 1 eak check, 1h19 inspect ton rev ca I ed a &mall 4ml)unt or sodium haJ been deposlled on the valve. but the amount was on the order of 10% oC that wh tch had been pre vfously observed. The valve was cleaned and thl' system w.1s returned to service, ll was decided that the surveillance of this l>ystem should be increast.>d by adding an annu,11 inspection and cleaninf. of the check valvQ.

5. Nl tro.a..en Blower Cont ro 1 ~witch ~alfunct ion

During the pcrforman~e of the surveillance test, LTr SA-0-5, Semi Annual Test of Electrical Distribution System Logic on July JO, 1971, a maHunction was detected \\*htch prevented a nitrogen blower from starling. The sequence or events leading up to the detecting of the ~alrunctton was as follows :

No nltrogel' blo-..,ers were operallng. The "blower preferred" st;irt swltc11 was in "position 3" (No. 3 blower), No. 3 Blower control switch was in °pull to lock" position (blO\\o*er could not start). The No. 3 blowe1* control switch \\olas shifted t<' the "after trip; ' position, but the blower failed to start.

Diagnosis of the maHuncti'>n revealed that the resistance of the start-initiating contacts on the control switch was so high th:lt sufficient current flow could not occur. Visual inspection or L~e contacts verified that the contactr. were dirty or corroded and chat the nor,1u1l wiping,let ion oC the contacts on closing did not occur. The contacts were cleaned and the surveillance test completed with satisfactory results. The control switch has subsequently been replacc<l with a new unit whose contact wiping acti -*u vas vedf led to be correct. If a loss of site power had o ~curred. and the diesel generator had started, and if the "blower preferred" switch had b-:en in "p,,sition 3," the blower may not have started automatic:ally. However. either of the other two blowers could have been started automatically by ahif ting the "blower preferred" S'l.'itch or another blower Cl'uld have been started by manual ~ctfon of the control switch for that blower. Since the temperature increase in the nitrogen zone is slow even with no blower operating. no immediate unsare or ~dverse plant condition would have occurred,

The "bl"wer pref\\'.'rrcJ" 'i1,dtrh Is r\\.>tHtn,*I~* kepl In "p1*~ltton l" to limit thl' lo,1d,>nth,' Jfr~<'i ~.. *:11.'r.lll*r Jurlu11,,tut om,H l c lo,,Jh1f,*

Only in the unusu.. l) c.'vcnt tli :H Xo, I hl,wer *.1.1s out 1,f SNVh'~

might the So, 3 h hw,r h.1v\\'.' li,*l*l~ si.!l,*c ted (,) r \\\\rctl'frl.'J slartiog.

A pre-l oad stress of 3000 psi was ('9\\JhlisheJ ln th~ dutcr heJd h~'>lts on April 18, l'J'/1, aftn st,1hlt-tt*np"r.1turc c.-onJJtfons had been attatncJ uith a sodium t~rnp c r at urr of less th3n Soo*t. The inner head b~lts were r~tensinneJ to a pre-load stress o( 7700 pai whe n th~ heaJ ~as relnstallrd fdllnwlng the IFA Installati o n,

The sodtum c~ala nt r1mperature chan~~s were )imfted to IObF/hr for temperature changes ~re~Ler than 12s*r. This rAte prevents the comhjned pre-load anJ tcmrer ature induced bolt atreaaes from exceedinR the ASHF. prcssurf v~fSfl code allowable valu~s.

The 10°F/hr t<'mperaturt> change rate further lengthened the time required to Jecrcase the te.mpC'rature to less than 400°~* for fuel surveillance. The possibility of fuel rc~oval and insertio~

at teftlperatures greater than 400°F was investigated, Data pre sented in the FDSAR showed that the stresses resulting frorn in serting a fuel rod Jl roo~ temperature (90.f) into sodJwn at 400°F do not have a significant effect on the predfc ;r' fatigue Uh o{ the fuel rod. lnsHti o n of a fuel rod into

• uun at temperatures above 400 1 F will not reduce the predic * (atigue llfe 1( the initial temp~rature difference between t fuel rod and sodfwn does not cxc~~J ll0°F. This is true for clad temper

• atures up to 800°F. (Ref. ASH£ Code Lase 1131-1 which give s a

~ingle fati~uc turve for high alloy steels.. t tG'llperatures of 800 6 F or le s s).

Tests were perf,, rmed to determine th<' ~ooJ-d o,..n rate for a fuel rod after heating the rod {n the v;jcuu111 di.stll.lation statlon to

]00"F. The coolest point on the rud was dctemlned to be 285°F after 20 minutes coo ling in the rcfu<-ling cell. The time to transfer a rod from the Jistillatlon station to the reactor (fully inserted) is l es s th,rn 20 m ln u tes.,\\ sodium tc111per.1ture of 57)°F allows inscrllon of a heated r~d without cxcc~dinP, the 310 °f t~per~tur c Jlfferenc('. Reinsertion of fu el rods into the core a(ter he,1tiilg ln the,JJstiJ Jat Ion st.H lon to 700~ is now accomplished wlth a ma,tlmum sodium tc1:1perature of 575*.

During re,,ct or operation at low po\\Jer on June 10, 197!, a 111aJfunction of a com~1<.1nent in the cr.1crgenc y p o wer supply Cor the fl\\a1n primary pump was Jetected. The malfunction did not affect the coolant flow r.ftP under nonnal opt'Tatfng condition s. Howev er, if a plant power

Joc;s haJ occurr,,J, lh,* primary,,rnl..1nt flow r.itl' ;iftl'r rc.1ctl1r scr,1n \\/,iulJ h,1v,, b,*t*o,lhoL1t M) perct ' nt,,f tht> normal v.1lue, lhls w*.>ulJ result in,1nly,1 slight in~rl.',1St.? In r~ilC'll'r c,.wl.rnt tc:mp1Jr

1ture,Jurini the first r.1!1111tc,ifter J pl.int pu1,~r loRS,

\\o.11t>n the ma! fu11ct t,1n w.1s ll iscc,vc *rl'd, the r,,.1ctor :Ms shut Jown unt'l repatrs i.*"rc n':-pl(*tl.'J.

A f lvwhecl is pr,wiJcd for £>ad1 r.iotor r,cnl'rator set to proviJe.i tenpornry source,if 1:11crgy fl,r the r.1.ifn ptiniJry putnp power supply in the event l)f loss r, f pu*..-~r toJ th" M*G !>elS, When such l<.)Sll of power occurs. the gcner,ttnr excitation is ~utoMatically switched Crom the nornal recttfiP<l a-c RUpply to the 125 V d*c storage b.1tteries, A follower circuit n3fntains the battery surplied excitation at apprl,xirnately the Siir.lt voltagl' as the r.~1 r111,1t excita tion to minimizl! the.:h,1ng1.? fn cl1of.1nt flow rate on loss of normal power. The excitation ts maintained nt a constant voltage for a short t im~ (;ihout 20 1h'Conds to l ndnu te) after lC1ss of power.

A time,Jclny rel.iy is then,u:*tuatcd to reduce the excitation voltage to zero,Hlu prC'vcnl ovuheat lng of the f leld windings after the r.,otor-ger.t'!r,Hor set rotatl1.1r.al spl!eJ falls below the v.11 ue rcqu i r eJ for.: frq1111t ~ coo 1 i ng of the w Ind ings.

During routine data coll~ctton 1 an operator noted that a resi~tor tn the follower circuit for M-G ~et IA was overheated and that the follwer rheostat was Jrlv~n to a low voltage position, The follower rhe,>stat for M-G set 1B was In II position wt,ich would provide full flow after power Joss occurred. The reactor. which was operating at crltlcality (zero power), was then,._ut down to permtt correction of the malfunction,

The overheated r, *-slstor was in series with a time Jelay relay set of contacts a*1d the rhcost,1t motor... tnding across the 12~ V d-c po'-'er supply. The relay contacts are enclosed in a phenolic case and are actuJt~d by a plastic plunger through o hole in ti:*~ siJe of the C,1S(', lnvcslig.:ition indicated that the plastic plunger \\,1as stuck in the hole anJ wns holding the contacts in a partially closed position. The relay had been actuated last on June 2, 1971, when a pl.mt polo.'L't voltage dlp caused transfer to the emergency pol.'er supply (rly,.*hce1) system. After the rheostat had run Ul)'Jll to th~ zno voltngc position following Joss of nonna I power, a limit switch opened to remove power from the rheostat motor 1dndin 6. \\..'hen normal power w:is restored, the rheo,tot movt*d to a higher voltage:, positkn. clo~ing the limit switch. Th~ control cfr~uit could then energize both the raise and lo\\."~r ~1 nd ings c,n the rht'nstat r.iotor. The motor was not J.m.1ged, but the res J s tor bl*,.1r.ie ovcrhe.lt eJ.

The malfunction was corrected by ~nlarglng the hole through which the plunger operates, \\11hrlct1tlng the plunger, and replacing dam.1ged clr cutt b~ard components.

9. Instrument Nltro_gen Su_p.E_l.Y 1.ini:s to..Y!_lves In Nitrogen Zone

Item C.5 tn the Eighth Quarterly Plant Operation Report descrlbcd tht! bre.>king,1 f the instrument nl nosen supply line to the Reactor OvcrCJow Valve, An Inspection o( all such linee in the

~ltrnK<'n Zone w;1s pcdormC'd Jurtng rhe &Ullllller outage, The In spection ~as intcnJed to detect damas~d lines, lines with tn*

adequate len&th for flt>xlng, or inadequate protection agtlinst vlbratfon, anJ the possibility oC work-harrtenin1, One pote : :tially damaged line was removed whtch had a bulge near the ferrule, All other lines ~ere found to be tn satisfactory condition,

0, Saf e~y Revitw and Auel It Ac.!£!._i_t}c.s

1. The s(*venth nr,~t ing of th£- Sat et~* Rcvlew CollWlli ttee l>'as he 1.d at lht! site l)O June 8 and ), 1971.

2, lwcnty-one meetings of the Sttc Safety Committee were held during this qu~rter.

). <inc trip W.)S 'il..tde to the site by C. E, pnsonnC'l frM the

~un~yvale office to review plant safety.

r

• TAtl.f. I

~ tA£_!_0J!.2l= RA.'i s

O~:tE h'UMtf:R

---

~*--40-*-

'>lb/71 Sil£: Power l.os:1 During Thunderstc,rm

S/8/71 fRfO fest (tr V-1) 80c@ 1 MW 12S

S/ lS/71 fr.LO fest (TP V-1) 76~@ 1 ~h 126

S/! 7 /7 ! FREIi Tc:H (l'P V-1) 9)C @ 2 MW 127

S/25/71 FRf.D Test (TP V-1) ~Jc@ 2 MW 128

5/25/il Operator F.rror (lmftOper Range Change WR.~ 12) 129

',/26/71 l 30

S/ 26/11 131

\\/28/71 Spur lou11 Trip L-.'R.'i ~ 2 Whf le f.witchtng Ranges

( 1 2S x 10~1 to 40 x uP %P) 132*

S/29/71 Spurious Trip \\.'RM 12 While Switching Ran~es (125 x 10-l to 40 x 100 XP) 13)*

5/ 29 /11 Spurious Trip \\IR.'112 Whlle Switchtog Ranges (125 x 10-l to 40 x toO ~P)

6/l/71 Spurio~s Tiip WRM 12 While Switching Ranges (12S x 10- to 40 x 1 Zr)

6/3/71 Spurious Trip WRM ~1 While Switching Ranges (125 X 10** l to 40 X 1 %P) l J6*

6/ 6/71 Spurious 'fr ip WRM 02 Whil~ Down~taling on Reflector Rundown (40 x 10-i to 125 x 10-S ~P) 137*

6/7 /71 FRED Test (TP V-1) 93c @ S H\\.: 138

6/7/71 FRt;D Test (TP V-1) 93c @ S HW 139

6/8/H FRED Test (JP V* l) 93c @ 10 MW 140

6/10/71 fR[D Test (IP V-1) 9)c@ 10 MW 141

6/12/71 FRED Tesr (TP V* l) 9Je@ 10 !i\\l 142

6/13/71 FRED Test (TP V*l) 93c@ 10 MW 143

l These~ra~s were related to the effects or the transten* Th " ~ teJt on ~/26/71.

e cau8~ v~s correct~d as described ln ltem 1 on~ J~ of this rerort

-22 -

• **

• t,

• r OHISJTIOP..S

ABC Air 81.lst Cooler APS.\\t:>: f 1 h ry l'r t~.i ry Sy!; tern A.RH Arc-a Rad iat fon Honttor ASS Auxiliary Seconcary System Aux, i\\uxllicir~

BRO Breeder Reactor ~epartment Ci' Corrective rr~c~dure EM El t.- r r ~* *:-lag net ic EP Emerg~ncy Procedure FCV flow Control Valve FRED Fast Reactivity Excursion Device U'A,,slrument~d fuel Assembly i::'ST lrr~diated Fuel Storage Tank IHX lotennediat.e Heat Exchanger IRM lntermeJiate Range Monitor LTP License Test Pr9cedure MPS Main Prf~ary System MSS Hain Se~ondary System HFSV NeY Fuel Storage Vault PAP Pump-Around-Pump PCV PresRur~ Control Valve PM Pre~entive Maintenance PTP ProvfstonAl Test Procedure PVT Priffiary v~nt Tank Rx Reactor SRY. Source Range Monitor TOP iemporary Op~rat{ng Procedure TP Tc!>t Procedure WR."1 Wide Range M~nitor