ML19322A359

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Forwards 780525 Proposed Ltr for Establishment of Master Svcs Contract Task 68 for Signature & Transmittal to Util. Supporting Matl Including PA Sherburne & Lh Bohn 780323 Memo to Jt Janis Re Util Rapid Cooldown Encl
ML19322A359
Person / Time
Site: Rancho Seco, Crane
Issue date: 05/25/1978
From: Janis J
BABCOCK & WILCOX CO.
To: Jeanne Johnston
BABCOCK & WILCOX CO.
References
TASK-TF, TASK-TMR NUDOCS 7910040526
Download: ML19322A359 (41)


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. THE'fASCOCK & t$1LCOX COMPANY PWER GENERATION GROUP L

x

'l J. H. JTiNSTO'i, DISTS.tCT SALES MANAGER From

/ /4 % ? h e.-. m J. T. JANIS, SERV CE MANAGER l

ses ao s I

Cust.

File No.

I SED or Ref.

Subj.

Date F.

MASTER SERVICES CONT.uCT A?2ITICN MAY 25, 1975 Td Qq li................................%.

IT b

b3 Attached is e propesed lettar fer estr.blishment of Master Services Contract

[f, Task 65 for your si;; nature and transnittal to SED.

If you have any hg4 questicus or require additional infernatien. please advise.

JTJ/hh Attach-ent

[Q cc: CO Andersen fa R. 3erchin M

RP Breedicg 1

JM Burn-tt H3 Muir d

BA Karrasch irgj CM Olds

'td JD Phinney Inq CG Culberson - SPR-330 File k.

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One Cavym.a 5:,eet. Se Fraws. Ca:.t bill Tep HIS)421-34S4 F.zy 25, 19 78 Mr. J. J. P.atti=ce Assistent General Manager 5 Chief Engineer Sacra: ente, &=icipal L':ili:y 0 strict i

6201 S. Stree:

Sacra: ento, California

Subject:

Master Services 00=::a :

SMUD Contrae: 6367. 3G' No. 595-7072 Task 68 - Analysis cf March 20, 1978 React:r Trip and Rapid Ccoldo'.~ Transient

Reference:

1.

B&W letter, JT Janis to RJ Redriguez, da:ed March 23, 1978 2.

B&W 1etter, J' Janis to RP Oubre', dated April 5,1978

Dear Mr. Matticioe:

As a result of the March 20, 1975 Less of NNI Fewer Incident cad subsecuent rapid cooldm transie:t, 352 was requested te perfer. an evalua:ics cf the ef fects ef the transie:: ce : e :leactor Coola:t Syste: (RCS). The follcwing Task Prepesal has been prer: red to cover the analysis veri perferred :o date and to cbrain your appreval fer add *.:icnal analyses : -fdress NRC concerns and deter = ire the long ter: effe:: en the life cf RCP :2si:gs.

his task is prepesad under the teres and cc ditiens of the subje:: Master Services Cont ac:.

Task 68 - Anal sis rf the Mar:h 20. 1978 Fe :c Tri z.d FM id Creldewn Transien:

Task 6S Evaluatica of Tra.:sien:

Sco:e The C :pany will perfor. an evaluatien cf :he effe::s cf the ::ansient a.

conditiens en the =sjer cc:penents of the RCS an:i the uelcar fuel assc.311es on an expedited basis and pre.".de SM"3 wi:h a lette reporting its rece-endatiens. 'his evaluation will be perf:::ed based c tran-siec: data previded oy f C 3.

b.

The Co:pa.y will perfor= a detailed QA review cf the calculatiens and analyses perfor ed. in:'. ding verificati:n of validity of the 1:;:ut A

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-TASK 6 8 i

h MAY 25, 1975 I

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t Estimated Cost i

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Charges vill be en a ti=e and caterial basis at the appropriate Master Services f

j Contract rates in effect at the tire work is perfor:cd.

Ite= (a) above is l

coepleted and ite= (b) is in the report preperatica stage. Through April,

)

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$26 MH and 0.5 ce=puter hours have been expended and it is esti=ated an j

additienal 200 151 vill be required to ec=plete the task. Travel and living j

expenses vill be billed at cest.

j 1

Schedule 1

[

l Ite= (a) has been cr pleted (Reference 1).

i l

for trans=1ttal about July 1,1978.

Ite= (3) report should be ready j

Task 68 Follev-en Tracture Machanics Analvsis

_ Scope In task 68-01 (a) above, a quick and conservative fracture =echanics a=alyis

~

O of the reactor vessel beltline region and outlet ac::le regica was perforced.

t This was an ASMI Sectica III type analysis using a postulated flav si:e of 1/4 the vessel thickness.

The factors-of-safety calculated for the beltline regien and outlet :z:le regica are 1.8 and 1.2 respectively.

Since the NRC staff expressed an interest in analysis of facters-of-safety for s= aller flav sizes, 3&% propeses to perfer= additicnal fracture cethanics analysis i

for the reacter ccelant pressure boundry areas rest susceptible to flav greuth.

These areas are the reactor vessel beltline regica, reactor vessel outlet and inlet nozzie rc;iens, and the lover head of the CTSO just belev the tube sheet to shell j unctica. The analysis will be perferred for a series of flav sizes ranging fr::

flav depth of abcut 0.5 a/v.the tinicu= reportabic flav si:e defined by Se:tien XI to a The final output of the analysis vill be a plot of factors-of-safety versus flav sizes and plots cf facters-ci-safety varsus time during the transient for several flav sizes.

The applicaticn of these curves would be that cace the desiratie facters-of-safety are estaalished, 1

SMUD.vould need enly to de enstrate that it's KDT technique veuld t ave detected the associated flav size during the baseline inspection.

Estinated Cost i

Charges vill be en a time and caterials basis at the apprepriate Master Services i

Centract rates in effect at the time verk is perforred.

It is esticated that I

approxi.stely 310 ME will be required to corplete this task.

e.xpenses, if any, vill be billed at cost.

Travel and living f"%

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. = * -

i

_._m

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BLbcockf.Wilcox TASK 68 y_W 2 5. 19 78 nl w-

=

Schedule It is estic.ted that the sys: tire :o co :plete this analysis vi'.1 be eight (S) weeks f ren date of task autheri a:ien.

Task 68-03 f fect of T:s:sient

. Accurulated Tsare Far::: f Eeneter Coolant

?um Scepe Re effect of the large t.2 pera:ure a-.d pressure transie::s c the pu:p casing and cover is bes: evalue:ed b the respensible e:;1:eer whr ;<rfer:ed the 1

stress analysis en t ese p:=:s.

I: is believed tha: :hese ::::sients could have caused sere cyclic :- e s:resses which vill increcse ::e lifeti=e usage fcctor slightly. 35V si1* ::: ra:: vith :he en;ineering fi-who perferred tha original s::ess analysis :o perfern this additie:al fa:igue evaluatien.

Estinated Co_st t

ha ce,st quotation received fre= the engineering fir = is SS 102. This cost will be billed unde: the Frecureres: ter:s of the F. aster Serva:es Contract.

Schedule It is esti=a:ed that the sys:: ti=e to ce=ple*.e this analysis vill be six (6) h m ks.

D.

Vork on Task 65-01 was ini:ia:ed c the verbal autheri:a:i:= cf v.r. R. P. Oubre'.

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Work en Tacks 65-C2 and 55-33 vill be initiated up n autherica:ica of this tasA Ietter, 1

sw:

. v.g s;

This preposal is valid u::11.*u c 33,197S exce;: :ha: the :.-- any shall have i

the right to vi:hdraw er a cri :his pr pesal at : y :ir.e bef:re f:rral accep-tance by t'.:e purch aser and s.:seque:: acceptance in vri:ing by as authorized rapresenta:ive of the Cc:pa y.

i'd[;

b If ycu have any c.testices er re uire additienal infer:a:icn, 21 case centact ce A

or Joel Janis in lynchburg. Yet ray au:hori:e ::is task by sig=ing in the Sk epace provide:i belev and re:n ning the cepy to us.

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CF TDE E,'.CTOP VE!SEL OF THE S!D t";!T AT PA ;C!n S L (.

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V A fracture rechanics cr.:1ysis of the reacter vessel has teen perforced usir.c the conservative ao:ro ch c;;lired i ice ASPE Cede,Section III, 4:endix G.

j 5pecific details of tne ana:j:ical ccroacn ure dccurented in Ct/. Topical

,P1 Repo rt E A.'i-10346 A, Fev. 1.

$U Analyscs ucre perforred e ::2 tuo rest critical areas Of the reactor ves: I-

@@j the beltline rc:ica and trc cutlet i:::le recien. At 6."e icv:es: tcrporaturc L 'f4 during the tradient tha - at: rial is still in the u; par t 21 f ic ;ien (ductilo

@p behavior}. Die to tre 10.*

c.el of raciaticn, decrad::ica to beltline rer, ion r.aterials is rct significa. encugn :c precute a inift in the trar.sition h%

reference it.c:rature. Cc.s a:ucn:ly, P.e bal-li a regic materials crc aise y

at the uo;;cr snelf tcug-'.nass ragicn.

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L factors-of-sarcty for :! e tel:line re;icn and cutlet ner:les hcve b:en calcu-lated as fe;icss:

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EIR

u. s%

F. of S. =

.te-t,In rIt e

W

~

where K is tic reference stress intensity f:ctor yg K, is e.e stress h:ensity facter due to pressure g

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K is th grad:.e stress ir.:ersity fac:cr due to the thercal

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$ylM ine fceter-of-safety fcr t e tcltlir.a -e;ien is 1.8.

. ft The fac.cr-:f-safety fcr r.c c., let r:::les is 1.2.

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mf Detailed calculations arc previdcd cn sheet 3 cf 3.

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It should be racc pi cd 151-this is : very cc servative ar.alysis. A postuls cd G4 flaa size cf 1/0: 1s ass >. sc f:r *.h: tc.li.0 ragion and ite 3.0" nc:zle cerr r

??'d flaw is tsse cd for tra : :'s. n:::lt. Tr.e ::terial fra::ure tou-hness (reftr-h ente stress irts sity vcl a' _:cd is I:0 isiJi.

Finally, the calculc icn T

Q of th: str:-sscs assccic::t. ':n tr.e :

.si c.t is cc.:scrvative.

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JM Burnett A '

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CW T,runy/3.W JR Burris THE' BALC0CK & WILCOX CC'4P ANY P6*'ER GENERATION GROUP

' J. T. JANIS, NUCLEAR SERVICE, NPGD '

e F : wn,L. q P. A. S!!ERBURNE/ L. II. B0!!N, STEA5! GENERATOR UNIT

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Cust.

File No.

SMUD or Ref.

S u ej.

Date SMUD RAPID COCL30;;N--EFFECTS ON OTSG INTEGRITY MARCil

^3, 197S g....~............-.................,

1.0 RECM" FNPATION Our prelininarv assessnent of the potential danage to the SMUD stean generator during the 3/20/7S rapid cooldewn transient is conplete.

Based on that assessnent, we feel that the stean generators have not been adversely affected and that the SMUD plant can return to power operation with the following quali-fications:

(1)

Plant operation should be limited to 75% pcwer pending (a) ccafirnation of transient data supplied by SSTJ3

(])

to date, (b) QA of shell tenperature calculations ade by B5X, and (c) review and approval of CTSG tube ' cad calculations nade by C.

N. Bruny (M'.'X).

(2)

Confirnation fron SMUD that the Loose Parts Monit:-ring Systen is operational, especially in the area of t'.e upper tubesheet.

In additien, SMUD should be inforced of E5X's intenti:n to perfor. an inspection ci the steam generators during the next outage.

2.0 DISCUSSIC'.

Figures 1-3 give the histories of RC cold leg tenperature, stenn pressure, and CTSG water level as reconst ructed fren d ta suppitea by SMUs.

. e aj or concern with the stenn generators lurin; thir-transient is whether the tubes have plastica 11y deforn:3 ce to :::e large axial tensile leads inposed on ther.

If this is the case, the tube 1cid felle::in; return to "ower eneratien s.

e ore cour n s s ive and tube natural frecuencies '.ill be lotsr::.

The consequence of lesser tube frequencies is reduced sa fet:. na rgi n for fluid e'..wtic vibratica (Conners' r.e chan i sn) of the periphe r:.'.

t ubu (up;.e r span).

l l

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J. T. JANIS P.'A. S!!ERBURNE/L. !!. B0llN MARCll 23, 1973 L

E t

To assess w.%:ther or not the tube yield strength was exceeded

[O]

during this transient, an estinate cf average shell temperature b

vs. t in.0 was nade.

A plot of the averace shell tenpe ra ure as

?

ralculated is shown in Titure 4 Frem this calcula ion, the F

maxinun tube-to-shell te perature dif ferential ( t.T) is 170 F at 0515 hours0.00596 days <br />0.143 hours <br />8.515212e-4 weeks <br />1.959575e-4 months <br />.

(Note th t avera;e tube temperature is equal E

to RC cold leg t e.pe ra t ure. )

This informatien was transnitted verbally to C.11 Bruny at

4. Vernor who subsequently deternir ed 5

that 1700F tube-to-shell :T dces not result in a tube stress a

greater than yicid.

Essed an this information and on cur iudge-F ment that the calculated average shell tenperature is censervative, we concluded that the tube stress did not txcecd yield and that the tubes 2.ete nor clastically deforned.

Due to the prelininary nature of this.ssessrent, he;.ever, we advised

t. hat plant operatier.

be restrict *;d to 75'. power perding QA of the calcul:.tions.

Additional effort is required by Mt. Vernon personnel tc assess the ef fect of the rapid cooldown on the OTSG cunulative usage i

factor.

'this effect will be determined and forwarded when complete.

~

3.0 CLOSURE It i, our understanding that the above coscerns and restricticas f

were verbally transnitted to 5?:UD by B. A. Karrasch on 'lednerd:;.

O a f t e rnoca, ?.la rch 22, 1978.

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i THE BABCCCK & bit!.Cox CC:'PA:1Y POWER GE :ERATIC:: GROUP HO l oistrieutier. tist o

,. f /*'

a' fro".

G. !!. Olds - !*3 nager. *?u: lear Service Departrent.',

505 H M J. C. Ped cr.s - 'anager, Ir.gineerin:; ~. part ent _

Cust.

IIIC NO-or Ref.

Suoj. 54)) TJ;I :ncident Recovery Teen Date P. arch 21, 1970 g..........................................i, a

The Ranch:-f e:c plant suffercd a less of the !;11 Syster. for approxirately an hour on 3/20/75. A severe plant transicn: resulted.

A task force is appointed via this rze.mo to reconstruct the event a :d to investi-gate any sig.ificant ef fects on the ?;55 cquiprent insolv:f. The task force is expected to drite EI. ' re :.t er datiens temthe custc.sr tastd on their findin;s.

In additicn. they will assist f.:;!] in gaining :.RC ccncurrer.ce with returning the plant t service.

The task for:e vill be headed by B. A. Karrasch, *:ho uili work through J. T. Janis with the S' C organiza:icn. Bruce will be assisted by J. J. KcIly.

The Licensir.E represcntati.e will be C. S. Bar...arth.

d. !!. Burnett vill cecr: irate C rpenen. Er.;intering cart ci ation.

P. A. Sherburne t

and J. R. C.rris have started 0T53 ccicuiaticns.

J. A. Cutants.till cc:rdir. ate all 2:.ivities of the Central and Icstrumentitien Sectioi.

R. 11 int.s I.d A. ?!. Erc..n are prc ceding to the plant to assist with the invc.tignic..

Ot W s rg, te added : th:. task ferce a: tha..cr! proceeds.

Top pricri 3 stuld he essi:r.ed to these cctivities in crc.-r to return the pla.t to scr'. ice 7s scen as possit,le.

G 3,.n..-

cc:

J. H. **::*:illan

J. T. Janis s

D..:. I':.y : :.ry C. S. L:r.arti R. ::. E Al J. ;4. E rr.e :.

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Te*c;e:re: (5041384 !111 March 23,1978 Mr. R. J. Redrirucz Manager, Nucles: Ope raticas Sacrc2nto 2:n-Ccipal Utility District 6201 S. Strce:

Sacra:cnto, C:liferr.is Subtett: Ear.cho Seco Nuclear Generating St tica - Unit No.1 Evaluatica cf NSS Coold:en Ircasient

Dear Mr. Ecdriguez:

EU.' has reviewed the data providcd by SE'D regardin, the March 20, 1978 reactor trip nd resulting cooldcwn transient, and have perfor cd the folleving cvaluatiens:

1.

0 Evaluatien of EC7 seal perfernance data prier, during cnd subsequent to the transient.

2.

Evaluatien of trrnsient conditiens with respect to RCP's cad CD: 's.

3.

Evaluatica of transient conditiens with respect to fuel assenblics.

4.

Evaluatien of trcnsient cenditiens with respect to RV, RC piping, pressuri ar, and DIS ~,'c.

As a result cf there eveltaticns, Irs' cencurs with S!.""D's intent to return Kzncho Sece to pcvc. cpuratica at a pc. cr Icycl at er belcw 75*. full pcuer with the fell wing recc.rcadaticas:

1.

The fclleving==cuvering linits be c; plied for this plant startup:

a.

The rutxirun rate of pcver increase belev 20*. full pcwcr shall be 100 per heur.

b.

Ti.c c:xirun rate of pcwcr increase betucen 20*. cnd 40; full pc.er shall be 300 ;cr heur.

i.beva 4"*. full re.cr, cscalatica shall be lirited to 3"; per hcur.

c.

2.

Incret. sed curvcillence of the leese parts renit: ring systen for at least a cne vec. p2riod.

m itwo [i,.! fy k & '.".tDs Cet;nny F { O.*)h.,.33 j 4.~.7

~.

6 Babcockt.Wilcox 0

Ju:15 TO nonnic z= r.xxc" :2. m78 l

3.

Perforcance of r. cperMlity cb ci of on-line c d red =-4't 20;I in.stru-en-tation.

4.

Establichant :f a procer ure for restering :.7;. pcuer in the event f a power less sni a cer.itt.cnt to establica oy April 7, lHs opera:cr instructicm3 f: i mediate cctic :: litit NSS transic t if :';I pcze.r

w. rot be i=ciictely rcr:ored.

5.

Surveillance cf Tri:ary and sece:h-f radiochenistry en a zici.=: ef a daily Lacis fe:.: Icc:t ene veck fell.:ing et:r:np.

-B&'* :: POD's cencurn=ce with e;crctica cf Ecacho Secc cheve 7f full ; rer is centingent u,,cn c= RA cvaluatica of d :a jnput previdsc by E:.'"D :.ad cc 17scs perforced by 14% F.:gineering, cnd you rill be inferred cf ec=pletica cf :nese activitics and cc:==currence in a ti=ely t.anner.

In additien, ESW is perfort.ing ca cvaluatica to deter ine the effectr cf the transicat ccaditic s en the Kaactor Cool::t Syste accu nlativa usa;;c factor end vill cdvise yee ef these results. As a further eccsere ef verificr~len of OISO tube inter-i:v, I!/.? requests additimal inspectica ef the C!SG ::bes during your next nfceling cura.;e. 20se inspec:ica recc=encatic:s will be forwarded to 5:0 sl: g with 55.;'s prc;esed rcft. cling inspe :len plc prier to the outage.

l If you have any questiens er require affiitional infer:stice., please sivisc.

I Very truly yours, 1

Y ec1. 3:.nis

~

Service n: sger JTJ/hh cc: JJ !!attinae DG Raasch be::

' Eall r2 Oubre, s* S c '. ' -

Jil Jchasten

' " ~

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EA Ecraa.:h 1

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C:: Olds J3 Phinner R

.Ni. L u t e.e JR Taylcr iccord Center 515-11 T1.2 1,. g Ag r. ; m'T"E = T--J sc,.'n m {gmv T.%.A s. EM7;.4lyp m

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P. O. Cox 1:M Lynchberg

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y-SSE4 For discuss.icr: vich you c: .1 cony, harch 27. ye : reqc.ute.! s ch tris.c i stv of our ri:,c to pc.:r e w r ti c pa.t weekecd. Lected belcu 3?^

is t.52t cr.rerolo;;y s':.eving the race of chaage c,f power lenti for thu

@$1.

three rinz in pcver.

w'

~

s.

Critie.:lity 9 1637 3/24/73 G-207.

t1/hr 3/24/73

~

20-42.51 62/hr 3/24/78

, Turbit.e./Receter Trip at 2230 3/24/73 Criticslicy 0 011~.

3/25/73

~

0-23

&*/hr 3/25/78

~

3/2",/ 78 20-4u7 26 /hr 3/23/7s

-Y~4 40-55 3 /hr NN 55-M:

esacuti:.nv C:/hr cvar a 23:r.aur paric..

rep;+m p: m,,

w

, extendin;: into 312'/18

{

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.Practor r m cd to 10'S h k%h!1).

interA.fla:c r:::ge 4;;s 3/25/7S gg(pg s

{t;g$Wpigy 0-201 10:ihr 3/26/78 h

y$hird 20-50:

I71/hr 3/27/76 50-551 2:!hr 3/27/73 55-721 12:/hr 3/27/7T.

7.NW q%l+fhQ ~rm b

h You vill cete that on the riec to pc.*r fren 55 to 72: en mn Sy, SM;+#.3;.s

}'ttch 27 the rate of clange v. s..c 12: pe

'r.ei r. This ecceeded the e

r Rdd rcec recied rate of ch:nic n:wn to Ch'.:D 1:..aur Iceter of Eatch 23, 1970.

7.QQyg[it yy I request U/J teview thic. race of cht. p.ar C r. spend to 22:' J or ar.y eqf ect J

vhich it my b ve 1.c.1.

I would a,:pectine year response es soon as poc:.it,le.

?A:Jw 01/Q$

F.a cpec t fully.

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O P."t.CHA:IC/* MMiEUVER!:;0 T.ECO.t:E::DAT10::S REVISIO:I O

PANCHO SECO DATE JJ':E 3, 19 7 7 O

The followin; are the reco=: ended :.aneuvering lisits f or SMUD, Cycle 2:

1.

The ecxinus ra:e of poser incrme Leics 20% full power sh.11 be 10:

6(f par hour.

f' 2.

Above 20: pouar, nor:21 operatin;; pro:cdures (Tech. Spec Licits) vill t

0' apply unicss the reac:or has operated t.: Icss than 20: power for core g

than 45 hours5.208333e-4 days <br />0.0125 hours <br />7.440476e-5 weeks <br />1.71225e-5 months <br />.

. r 3.

If the pever level has been bc!ce 20; full powcr fer greater than f or ty-ci;;h: (l.3' hours, the :. :i: = rcte of powcr in rease above 20%

full percr shall bc 3::: por hour.1:h a five (5) hour hold at 00:

tull power belc.. the power levci cc:cff cnd a five (3) hour hold at the Power icvel cu:off. These holds can run concur:cnt!.y with holds required by the Tcchnical Specificaticn.

4.

During the ini:ici power eseclation at cycle star:up er i::=cdia:cly

  1. 'leeing a con:rol rod in:crchange, :he ini:ial escalatien above :he p

75*. full power shall be li=ited to 31 per hour, vi:h a five (5) hour ho.'.d at the pcver IcVel cutoff. This hold can run cencurrently with Technical Specificc:ica holds where applicable.

5.

With the ex:cp: ion of itt.m 4 above, no restric: ions are placed en required physics startup :ests.

ft

) (5 0 l

.. T.e,. Ts X ? J-

/7UEL E:;Gl ::.ERI:;G SECIl0:i MANAGER v

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e T1tC Us CCOCK & )llLCOX COMPldY POUER GEf!EF.ATION GPOUP To j

O C. >:. oids. : anacer. ::uclear service Fro.

B. A. K.r ras.*, Manage r, Pl ant Inte gration.

ess e m C:s s t.

File lio.

177 - All Subj.

Date S!.JD C rld:.n Incident March 29, 1976 g..".......................................

On l'. arch 20, 1978, Sr.;D expericaced a loss of power to a substantial portica of :he non-nu Icar instru enta:ica (see details - Attachncnt 3).

Althcu;h the T. esc:or Protcetien Systen (p.?S) and Safety Features A:: cation Syste7 (STAS) functioned properly, SM'.*3 s:ill expericated the =ost severe thermal t :nsient en any E5*J plant to da:c. The subsequen: investiga:1:n pointed cc: that additional guidance to our opercting custeners in the area of 11:1:1:3 potential events of this nature is varran:cd. A:: rdin;1y, the Lt inecting Daoartsent recc, ends that our operating plant cus:crers be in-fo ccd of this incident, and su;;gestions be r: ado on hev to cini=1:e the plcnt ther al transient for loss of l0 I and oths: si ilar eve s.

Attach:ent 1, a sequence of events, and Attachten: 2, a series of descri;:ive curves, are Q provided to assist you in preparation of a custener let:cr.

In addition, the following rccc=endations shecid be cade to assura proper operstor a:: ion for events of this nature:

/

1.

Operctors should be trained to recognize a loss of ;ever to all or a cajority of their !O;I (indica:cis fcil :o cid-range, aute:::ic or etnual transfer to alternate instruccc: s: rings brings no respcnse, etc.).

The loss of ;:ver is er;hasi:cd here rather than the failure of any one instr'.::ent er certr:1 signal. These citor events are adequately covered in our p:esent si ulater course.

2.

Given that the operator can determine tha: he has los: p0 cr to all or nost of the 20;I, he should know the 1 :a:icn of the power supplics cad power supply breckers end have a precedure available to regain pcs cr.

3.

If the fault cannot be c1 cared (e.g., the breakers to the power supplies rcepcn), he should have a list cf.nternate instrumentatica availabic to hi=.

So=e possibilitics ::::

a) ESFAS pancis b) RFS pancis e) TCI c.s MCI 1

f' f

f A,,

g*

[

_?

4

' Khrrasch to Oldz Page Two

~~'

Subj: St%D Cooldoen Incident 3/29/73 c) Remote shutdova pan *1s f) Local gages g) Plant Cc:puter Note thtt e:ch plcat vill be dif fe:cn: in detail

  • ut the list th uld be devcle;ed is advance and.bc oper:. tors tMroughly trained in its usage.

4.

The ab::: ins:ruzentatien scurces should also be keyed to cert cin critieni viriables to help the operator select his pricritici d-

.ng the cr.:r;,en:y cenditien. It is recognized that no pre cdu:.

t e.

cover all the possibic conbine.ticns of non-nu:1 car instr 2:en.s-frilures, havever, if the operator knevs he has an instru.:nt prebi:7 (as opposed to a LCCA er s:.: m line break, for exa:p* c). he can lirit the transicn by centrolling ut.ly a f v variabAes. These are:

a) Pressuri:cr Icvel (via h*?I or noml ra.keup pu.ps) b) ECS pressure (via presseri:cr heaters, spray, E/M relief valve) c) 3 tea:s gener:cor level (via feed flow, feedvater valves) g !j d) Steas generator pressure (via turbine bypass system) e, The pressuri:cr Icvel and RCS pressure assure that the P.eactor Coolen System is filled cnd :he stes genera:or icvel and pressure assure f.

adequate decay heat rc:sval.

,QJ In our opinion, the prcicrred solutica is to install safety geade s:ca:

generator icvel f astruzen:atien, str e: auxiliary feediater o:. a lov Icvc1 c:ca:

generator si,*:al, nd centrol stes: generater level auteustically, as is required t

4

]

on our IgoT5G plants. This :ny not be a pra::ical o ckfi: s:1ution fer the operatin; plants, however, this solution sh:ul'. be su;;:estcd :.a a poscibic v:y to assurc mini.a1 ia:: :sp2ci:7 days due to equip ent failure. Plant In:cgra:ie will be happy to assist you in the preparatica of the ci.stener letter.

9A f

f 6 sw BAK:jl ty Ja ec:

J. C. Deddens J. A. Castanes td D. H. Roy P. A. Sherberne l

R. M. Ball J. R. Burris T. M. Schuler R. W. Moore C. W. Pryor R. U. VI::ks L. J. Stanck J. T. Janis

,i' K. E. Subrke A. W. Brown

(!

J. S.

lulenko

3. J. Shepherd fE-

=

T *,

c. c....a : o a

J. J. Kelly H. S. Palne J. D. Phinney J. M. Burnette g

D. F. Hallt:an C. /.. Meycr A* t.irhvn:.;

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ATTACl2r' ;T III TM ihM scgw

)

  • he eper.ator was in the process cf changing a li'St tu!:

p; s

in a t u * '- ' u:'e r prescure transfer rwitch when he dropped the bulb into the suitch : :

s ::cd the cwitch to gro-A ;rotective fuse ia t!.c circuit had no et :::

gj;fg f:

L: t2:a M@hqt before t'm pewe: -, ply renitor circuit ren cd the chor: en t!.c b_: :-? ::: cd the breakers t's the "Y" :nd ";" po.:cr supplica, n.i.; rewlted in ::: '. : - of t

l[fpM[M N

cpproxi :tely half the *:!;I sira Is

("?." powe r.eupply :c >ined c: ::p:e. end th? ability to trans fer f rec " bad" to " good" sig:mic, it should :: ;::.n:: d f

that h[I;p cut the utility ch.'nged the ceriginal EEU desi;n in the area cf t' e pr cr r

eupplies.

If the cri;;inal I1*' cenis;n vere installed, the incident -::' hrec

c p i.6?td tasulted in the loss cf the ability to tre.nsfer (scIcet) sig;nalc c '7 5%w@).

k

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r ST4JD;CE Or EVC;15 - 04:25(/d!) to 03:34(A'!)...

TIME IN f2.*T O

I.ost N:3I power supply cabincts 5,6, I. 7 4:25:35 (LW Channel "Y")

Inis caused a Icss of Tg; sipnals to the ICS.

BTU licits ran bech fecdwater, resultin;; in a loss of feed ster (actual Pa pcwcr ves 72%).

Reactor trip en hip,h pressure, turbine trip 4:75:46 on interlock.

Pressuri:ct cets relief setting was kncun to be low (=2225 ; i;). The ciectronatic relief was isola:cd d.:

to prcvious Icakate prebices.

The data indicates pri ary pressure vent *21.0 3 psig => code relief valve lifted.

Operator starts 1*?I pu p "S" to caintain p:r.

4:26:17 level.

Operator steps EPI pt:p "l.".

4:28:23 OTSC "B" goes dry. Data indicates that "A" 4:30 UISC probably also vent dry.

O 4:34:25 te prcosure.1,00 1S1 (1ov pressure trip set-point.

Operator increases s;ced of a YFP and feeds 4:34 "A" OTSG.

ais starts RCS cn pressere and

~~

teeperature decrcase.

4:37:16 SFAS actuatien at 1600 prig This starts li?I, i.?! and initiates aux. feed.

Aux. W valves are epened to full c;cn positica.

The systes takes no cutomatic atter;t to control stess generator water icvel.

4:40 RC pressure at 1475 psi;;.

It starts to recever fr:= this pcInt due to 12I.

Tave = 52SoF.

"A" 11PI pu=p sccured.

4:43:56 4:46:09 I.PI secured.

"A" 11PI initiated. Frem this point On. the 4:49:54 operator started :nd stcpped !!PI pt :s as necessary to -*tain nruri:cd Icvel.

1

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4 51:25 Secured RCp-D (T

=O50F)

This reduced (LCP's to threc l

3y, 4:47:27 j

OTSG "A" water Icvel - 599.7"

,f Speculate that e2 f t of tubes are not floodel 1(*

(at top) due to stca: line.arraar.crent.

'EW 5:00:00 Hourly corpu:cr leg prin:out Stena tc:p 3E30F (075. "g")

b.,

f Stcan picssure 171 psig (OTSC "L")

hf J;

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y Assu= sus Tave = Tsat ** Tave = 5800F

~

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5:13:47 Pcuer restored to !Ci: cabinets 5.6. & 7 cN t[

t y

T,yc = 2850F RCS Pressure =2000 psig 3.g 4 ggfA med Both 0750 full level ra=ges pegged high N$

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