ML20037A470

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Forwards Two Newspaper Articles & Questions Raised Re B&W Internal Analysis of 770924 Davis-Besse Accident.Requests Answers to Questions as Soon as Reviews of B&W Memos & Analyses Are Complete
ML20037A470
Person / Time
Site: Crane, Davis Besse  
Issue date: 07/19/1979
From: Ahearne J
NRC COMMISSION (OCM)
To: Gossick L
NRC OFFICE OF THE EXECUTIVE DIRECTOR FOR OPERATIONS (EDO)
Shared Package
ML19322D455 List:
References
NUDOCS 8002130022
Download: ML20037A470 (54)
v • d • e


Text

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'o, UNITED sT AT Es 7

NUCLE AR REGUL ATORY CO'AMISSION 8 '4,d*w.g,...fr i 2

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c July 19,1979 Y~._._,. :

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OF F CE OF THE 7/

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M MORANDUM FOR:

Lee V. Gossick, EDO :

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W FROM:

Jchn Ahearne d (1,

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SUBJECT:

B&W ANALYSES OF THE SEPTEMBER 24, 1977 ACCIDENT AT DAVIS-BESS E The two attached newspaper items, which appeared this morning, indicate that internal B&W analyses of the September 94, 1977 accident at Davis-Besse or. covered,infor.rietion which, if transmitted to operators of B&W power reactors in a timely fashion, might have prevented or significantly reduced the con-sequences of the TMI accident.

These newspaper itms raise marty questions, among which are the following:

1.

Were the memoranda referred to, or.the information in them, made available by B&W to the NRC prior to the TMI accident? If 50, when? '

What action did the staff take as a result?

?. OIf not, d6es this failure to transmit the results of these analyses

~~t-constitute a violation of 10 CFR Part 217 7.

1 3.

If the answer to Question 1 is no, did the NRC staff learn of the' analyses between March 28, 1979 and today?

If so, has the staff reviewed the analyses and what are the results of those reviews?

4 Jn the staff's judgment, if the information uncovered in these analyses h d been available to the HRC and/or Metropolitan Edison in a timely fashion, to what extent would the consequences of the TMI accident have bien mitigated or avoided?

I would appreciate receiving the answers' to these questions as soon as i #'

os
i ble.

If the staff has not yet obtained the memoranda and analyses or completed its review of them, please provide preliminary answers now and

.rore cmplete answers as soon as the staff reviews can be completed.

In l

cddition, I would like to receive copies of the B&W memoranda and analyses and the staff reviews of them.

cc:

Chairman Fendric Comissioner Gilinsky Comissioner Kennedy

omissioner Sradford Secy

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sngmeers Warnec.Srutter cc anger i.

ear.3e:, ore,-,. aree;.,.1.e..s..anc.

c cic eir r, in separate memoranduras, about a dan.

Mr. Kelly tc1d the cirnminee that be By B.DRUMMON'D AYRES ge ous sequence of events that.had oc-had be t seeking the " thought" of other s,.o% %,, y.n 7 curred when a Babcbck & Wilcox reactor engi.neers and some of his superiors.'

rmce broke down at Toledo, Ohio. The' However, bis memorandurn suggests I

wASlHNGTON, July' 18 - Two engi. two eng:reers swtgested that, c.ber that " guidelines" be sent plant operamrs stvrs ter the company that supplied the and asseru that "two recent events at the nuclear reac:or that broke dewn at hrt-e Operators of Babea k & Wilecx remctors, Mile island said scaiay that they had incJuding the one at Three MJte Island Toledo site have pcir.ted out that perhaps

, here a somewhat,sirnilar sequence of we a.re not ghinF our ettstomen enough w

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wamM their superiors a year earlier that a ser.ous acc! cent was possible but that events took p? ace, be sent guidance about guidance" about the cperation of some how to handje such emergencies, saf erv pumps.

the warning ind not been passed on.

At the Toledo plant, a pressure release In Mr. Dunn's memo andurn,he tells of "It j.:st slipped throcF.h the crack," a valve stuck open. threatening loss of the his " serious concern" tor "poten-f a!" fu.

. third e gn eer said.

cochng fluid eround the fuel core. Specia.1 ture coohng accidents. lie states that the The en;ineen, af! empicyees of the Batr.:#s & Wilcox Company of I.ynch.

safa>ty pumps began to replace the fluid, Toledo rituatien " points out that we have be g. ya. testi!ied before the Presiden. but piant officials tumed o!! the purnps not supplied suiheient information to tiaJ cr.ror: ission that is investigating the prematurely because a' meter connected reactor operatcrs." And be concludes March 25 accident, the worst in the his. to the malfunctioning valve indicated that"this is a ve y serious matter and de.

tory ci tMs country's nucJear power pro. there was,no problem. The pumps were serves our prompt attention and correc.

res*.arted m a sho-t wnlle, bowever, when tion."

P.

r rrn. All had been subpwaed. More the operators reali:ed the meter reading 1 fontiodotYobw

~P company officials were schedujed to tes.

was not correct.

Mr. Kelly and Mr. D tnn di4 not volun.

ti.y tornomw and Friday, At Three Mde lsland, the sequence wa, teer inforrnation about the mernoran.

Dr.cer q. nestler.ing by cornmittee metn.

sornewhat simila.r. but the faulty tneter

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bars, c ie of the enpree s, Bert M. Dunn, readJng wa.s not correctly analyzed for a formation only under ~ c;uestioning or dums cnd for the roost part revealed in.

s_;c. "Had my tratructions b-en fol. consederably lenger tirae. As a result, so schen cen!ronted with subpoenaed coru.

IN'. s.e would not have had core dam. Inuch fluid escapad from the reactor that 2

de wm.0d have hr.d a rr.in:r acci.

ments. such as tne memorander s.They arm ds..

  • A fpcAesma.a f or Babcock & Wil.

parts of ccre were e-qvased and began to 4 ere at a los to er;Iain why the com.

fpany had taken more than a year to 101 overheat.

ca ss d tr.at he wa s unab',e to reach com.

panvotiscials fcr elatsoration.

Warningissued a Week Later jl# up ca the:r recomrnencatie :s. Mr.

Seven days after the Dree Mile Islano iKelly said that at one poir.t when he

$ roe Radiation Escaped accident,Labcock &Wj)cox instructedits lr$*cLed on the pregress. and was told 7,.t a mdent severely dameged the, customers, including Metropolitan Edi- ;**._; his company r,as training reactor iuel r:43 in the resc or. In the af termath, son, the Three Miie Island operator, op-rators preparly, scm-ra dia tien esca p-d into ths air above about how 1o hand!c sutb emergencies.

The third Babcock & Wilcox engn-er to C.e ctr. tral Pe nnsylvan;a ele-tric plant.

M r.

Kelly's memora ndum, written testify. J ames F. Wa:ters, said that there M. Dur.r. and Joseph J. Kelly Jr., an-about a week af ter the second Toledo ac-had b-en a considerable amount cf dis.

cther Bat <cck & Vdcox engir,eer, told c adent, whs dated Nov.

1. 1977. Mr.

cussion of the roemorandt.m and the.

the s.x commissivo members that more Dunn's memorandum was dated Feb. S.

To!e<'o accidents within the company, t'.n a yer before the nre-Mile Island 1!i78, more than a ye2r before the Three But before rJything couM b* done, he conceded under quesuening. the rnatter t":,ter t C.cy had wamed the:r ruperiors, j Mile 1siznd accident.

" jest s; pped Ihrough the crack."

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. Jcorph J. I~elty, an enrineer for Babevek A TEcoz, testifyin; yesterday.

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!$noineers SayRehetor;BuHder IonoredWarninos.

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d Tbc Davis.Sessie accident invoired dharreed with I'elly's concerns: Wal-.

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,,.udden icss of coolbg water that te s told Kelly be thiought toe coera-f '

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' shut dowc the rucJear reactor.The ae-

'ters at DavieBessle: had acted.cor*

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  • eident occurred wben.a pretsure re-rectlyt besides, he staid, the accident 2abe et & Wilent Co. testified yester-,13ef talve stuck opes' venting thou._, wa3 ~of zio I=a; !tude."

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day they tried unsuccessfully to wz n ss.nds of rzllons of cooling wate.r away He was ennfused.," E'e5)y said of.

cuuomers of the pessibili;y of a nu-

.icGpled Threw hiise Island.

~. from tbe reactor, and plant operators. Waltm "Its.tthe Wa';1ters memo only ylear acdcent n=Har to the,one tb'D mistuen37 -hrctiled bel.he ps.mps

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{'Z:r "U Dunn, told the Kameny Com-T* e engin~< z. Jo eph J. Kelly and, pouri:s em he to Lir. Ds-- ** "

l. the reactor to 2:ake up.tbe difference..

Eel)y and Dunn s; aid -they t* lied While the nuclear core at Davi>Bes-ever-the " Jack of.r<esponse" a 2 ort investira:ing Three hide 1>

'~ sie was never exposed the way Ibe.

cistac:

Eabcock supemsors ::o Kelly's merno

- h::d for the Whi'.c riouse thzt they

ecre at Three MUe Island was, there

. d de:ided to pursuer the issue zna e r

, vTore memcas-to 3apecek supc nscr*

. events tha.t led to both accidents. De wcre st:,H n c simihrities in the 4::d tad rep-a:.e4 discussions with

' rigorously. D nn s.s id beJ wrote a ne.no to Jim Taylor, Insmager of the.

,canas ers ore what ibey felt was a pressure relief ra]ves at both places 11eeming dhn at 'Eabecek, trJ
:

reed to warn I.aocock customers of stuck open, releasing essential cooli :

hl= to address the afecidect at Datts-

,1:e pcolblif:y of a lotwfecciant se-water fro n the reactor; the pu:nps Sessie in a Inore consttr.:ctive way.

cdent Ilke tne o:e event.stliy suf-freed at Thrn.%th bland.

feediar. enmargency coolart to the

  • b=li=ve St ' Tole do Ca=b Beasle) cores v cre thre.tJed back or turned t 23 g c;-mu a, D ef.sn sci in the

,, T: da e of Kelly's f! s: memo was off, denying replacement

.o: 1,1i:77. while Dun w ot e his water to the cores. '

coelfsg me:n 2.ad this eve et eteurred in a rer. :cr vi all power.. 11 is quite

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prn meino Teh. 5,1978 more thu) j

-ope pi,r.,.coce-S the tiro ' a ed-a l yer-1efore Three Mih bland. Bab.

potrihn perbps pr >bable, that core dents ras th.at the Davis-Bessie ope a.

uncoverr rnd possita'e fcel camage ' '

cock cc
torners vrere never netified of ' tor gulckly realized his e mergency would t'au resulted."'

n'hi concerns.

- Talve was st:. set open and closed it Dr. :: said Taylor : responded by re.

. wrote f cllow up memo e -d had a'ter 20 2 inutes," Kelly testified-

. theussiorrs w2th people a bo::t the rtu:.'m= bis memo bac-k to tbe Nedear ne other difference was th2: the Service Divisionewhe:re Kelly bad run

. re-f to net-fy customers end I oper.

DavipBes sie peop!e throt*Jed back bte his oricht cheie. Dunn said *

, ated.mder the a.*sur::ption that new. two' pumps; the Three hiile Is3and he rever heird back ;and essemed that I

.-!:nr:ctions would be distributed to-. penile nepped al). four. To m e-eus:omers had been nctified of his i

[ cust e-e rs," s a d Du.c o. wh o is mam-

! t;iat's a sigt.ifirart c:dference."

eg e_,3, age c! emtr;,cory err ec 011mg ry>

. The a cice..

at Da rs t-B ess,e i

Pte-a nalyr.'.s for Embcoc': & TTileo: S pror:pted Ed.ly to write e memo to

.y :bberg. Va. *T.:t to =y knov).

sever B&tt* supervinrs in which he

. edre. cun:=c 3 w e re never neti' ed.-

,re=a=mected that z 2 -Babcock eus,

J Ke'Jya:d Dus: wid the Kemeny tosers be ;ive gu3dz,ct as to her to

.(c= ::.saio toel conce n.

w ere trig.

z v o.d a Q.il.ar ac:ident at their

ee f 6 mm aer! dent Sept 4, IF7. at

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.'ak2SFwssia r s!e ar plict of

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Do no bypas; or otherriae pre--

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Tci-do Idbon Cc.. whies. like

. rent the ac uz:ic= ciligh c-lose ;res-

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nia : Me1 epli:rn If wn ' sure i:JeeCen (e nerfecc7 C00ll::' un.

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.m ' bought i:.s ::vele s; pit:1 ider 7. y cenditict s esrept a nor:2al,-

in. 5:ecck & Wi!ros.

ee:1.olled pl :: st: down.", KeUy

."said tbe new instructh ns sbotud read.

ooet injectica is i::Jzted, do not stop it vnless temperar re is stab *e er

.' decree.si g an( *resst:.n:er ieve.1 is in-

. er etsing.."

l Eci!y said that 10 days a:ier he

'N ote his memo be reeelved a ::cmo-J g

.f n:o T. J. Wahers. a r :pe vher in t' e yp"

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Cust, l

.1 File No.

Generic or Ref.

S3 Subj.

Date Custoder Guidance On High Pressure Injection Operation November 1, 1977 lm.i...........,..........,........q..,..,.

-DISTRIBUTION B. A. Karrasch D. V. LaBelle E. W. Svanson R. J. Finnin

. N. S. Elliott D. ?. Hallman-B. E. Dunn v 0 M h % r>c,

T.ro recent events at the Toledo site have pointed out that perhaps ve are.

not giving our custoners 'enough guidance on the operation of the high pres-sure injection system.

On Septe=ber 24, 1977, after depressurizing due to a stuck open eIcctrocatic relief valve, high pressure injectiou vas auto-matica11y initiated.

The operator stepped "?I when pressuriner level began to recover, without regard to prd

=7 pressure.

As a result, the transient Q

continued ori vith boiling in the RCS, etc.

In a similar occurrence on October 23, 1977, the operator bypassed high pressure icjection to prevent initiation, even though reactor coolant actuation point.

system pressure vent beloe the Since there are accidents which require the continuous operation of the high pressure inj ection system, I vonder what guidance, if any, ce should be giv-ing to our custocers on when they can safely shut I recot-end the following. guidelines be sent:the system down following an accident?

a)

Do not bypass or otherwise prevent the actuation of high/ low pressure injection under any conditions except a nor:.al, controlled plant shutdown.

b)

Once high/I:v pressure injection is initiated, do not stop it unless:

Tave is stable or decreasing and pressurizer level is increasing and prinary prest.ure is at Icast 1600 PSIC and increasing.

I vould appreciate ;our thoughts on this subject.

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p s neco addresses.a serious concern ci &*n ECCS Analysis. bout the po,

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.tenti$.i' for opErdto'r7a'ction to te3n~*nS e 'high pr'es'siire infection' follo.u-'

l a

I t

ing thi. initial stage of a LOC.U 'fucc~'es$iful ICCS operation during scall *

, }.*.,1 breaks depends on~ilih'3.ccEEulated reactor coolant system inve6 tory as "vell

~

as the ICCS injection rate.

As such, it is candatory that full, inj ection flow be raintained from the point of. emergency safety features actuation * -

. system (ESTAS) actuation until the high pressure injection rate can fully F.:

4 cc=pensate for the reactor heat load.. As the inject. ion rate depends on t.be reactor coolant syst'en pressure,

t. catch-up occurs is variabic and cannot be specified as a fithe time at which 'a cocpens

~

xed number.

It is quite possible, for example,-that the high pressure injection =ay

., [

-successfully match up with all beat _ sources at riac t and that due to sys -

m.re:n pressurization be hdequate at some.later time r2 '

I concern here rose out of the'recent incident at Toledo.0% *%e;d

.The direct the accident During the operator terMnated high pressure injection due to an ap-

,'.parcut systen recovery indicated by hign level within the pressurizer.

..This action would have been acceptabic only af ter the prM y systen had,-

.been in a,subcoaled state.

Analysis.of the data from the transient cur-rently indicates that the system was in a two phase state and as such did

.,d

..not contain sufficient capacity to allow high pressure injection termina-'.

tion.

This becz=c evident at sone 20 to 30 -dnutes following tiermination of,'be reinitiatedinjection when the pressurizer Icvel again collapsed and injection had *

,,' A..

t c,

.... /.

During the 20 to 30 ninutes of noninjection flow they.

vere continuously losing i=portant fluid inventory even though 'the

  • pres-

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surizer indicated high Icvel.

.jtn extre=ely lou 7overcand c=tre=aly;.lov-burnup:;

Bad this event occurredT-b"eliEi7c=1tT dn a reactor at full power with otheEEh76~5IGPlfnifican:

burnup it is

-quite pessible, perhaps probable, that core uncovery and possibic fuel

. N e von 1d have resulted.

g I.

..1 The incident points out that we have not supp1ded Eufficient Infor:stion.

g to reactor operators in the area of recovery from 10CA The follocing' nile is based on an actecpt to al. lod"ternination of high pressure injec-tion only at a tine when the reactor coolant syste=. is in a subcooled sta te and the pressurizer is indicating at least a nor=al Icvel for ses11

$ hat during any f.ollow on,tran.sient would be no corse th reaks.

+

o accident.

h therefore...--

', recoceend that operating procedur..es be. written:

  • to allow for terninstion"o'f high pressur.e injection under the following~ /

t-o conditions only:

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,. f 1 i'preisure injection has been actated and is flowing at a rate in

' excess of the high pressure injection capability c.nd that situation

~~"r:,...has been stable for a period of ti=e (10 ninutes).

E

' f. Systen pressure has recovered to nor=.zl operatihg pressure (2200 or c

equal to the corral operating condition (605, hot leg gs less than or 2250 psig) and system tenperature s.-ithin : he r or 630 F).

.a I believe this is a very serious matter and deserves our pro =pt attention,

c.nd correction.

Nml c cc:

E.W. Scanson

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D.R. Roy

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B ABCOCK 3.'d!LCO)' COMP A!1Y

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'co GEDERAT10:1 GROUP

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k) s !. * ' _ ".. Q - -- - -- - - ~ ~ "

Jim Taylor, F.anager. Licensing

.,j '//

a tos 4as.s Bert M. Dunn, Manager', ECCS Analysis (2138) /*~ti*'

~~

File No.

t.

or Ref.

Date p.

" February 16, 1978 Operator Intetruption of High Pressure Injection 1,

I

w.. s.,...................... e..... s,..,..t r.

In review of my 'carlier neco on this subject, dated Februar,/ 9,19.h8,Tield*

  • 1 Service has re'co== ended the following procedure for terminating high press 6re

~

injection following a LOCA.

c~.

lou pressure injec' tion has been actuated and 'is flowing at a rate in ex-1.

cess of the high pressure injection capability and that situation has Sa=e as previously stated.,

been stable for a period of time (10 cinutes).

termina-j

2.. /.t X minutes following thc initiation of high pressure injection, tion is allowed provided the hot leg temperature indication plus appropri-y ate instrument error is core than 50 F belov the saturation temperature y, correspoacing to the reactor coolant systen pressure less instru:i:ent error.

td the ter=ination of the high pressure injection X is a time lag to prevent requires further work to define ~

i=:ediately following its initiation.

It Its specific value, but it is probable that 10 cinutes vill be adequate.

l The need for th'e delay is that nort al ' operating conditions are within the above criteria and thus it is conceivable that the high pressure in--

l jection vould be terminated during the initial phase of a s=all LOCA.

I find that' this scheme is acceptable from the standpoint of preventing ad-verse long range problecs and is casier to' implement.

Therefore,'I wish to.,

modify the procedure requested in my first memo to the'one identified here.

cc: ' E.W. Swanson D.H. Roy 3.A. Tarrasch o

E.A. Bailey

~

J. Kelly E.R. Panc

~

J.D. Agar R.L. Pittaan J.D. Phinny T. Scott p..s. a t

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e..J. F..Ualters 1.

3. A. Karrouch, Mahar.cr, Plant I n t e,,. a t i ri __..
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883 **3 3 D. F. }!alleen, Mana;;cr. Plant Perfornance Services Sectica (1149)

% lM by Mk)

[.' Q-s 5.

Date.

Operator Interruption of Eigh Pressure Injection (RFI)

  • iugus t 3,* 1978 g...................................;.,...,.

References:

(1)

B. M. Dunn to J. Taylor, sace subj ect, TebruaIy 9, ' 2 975. ".;

,,. 2 (2)

3. M. Dunn to J. Taylor, sace subject, Ta5%hry,16,1978. -

I J.

.s

~

2eferences 1 cnd 2 (attached) reev end c change in E4U's philosophy for HPI f

systen use duri.; Icu-pressure transients.

Easically, they reco=end -leaving the IC'I punps cn, once EPI has been iiticiated, uittil itcnn be dcternined that

,the hot leg temperature f.s core than'.50.*7 below Tsat for the RtS pressure.

Nu ar Serv:,.ce,oeb.e';cs..tha.s. code can cause the PiS (including..the. pres surizex) solid.

The pressuriner reliefs vill lif t, with a water surge through the.

.~.

.:. r..

trge piping into the quench tank.- - -

Uc believe the follovir; incidents should be evaluated:

J... s

. "1 1.

If the pressurizer goes solid with one or nore E?I pu=ps conti_2uing t'o operate, vould there be.a pressure spike before the reliefs open which could cause.

~

damage to the BCS?

....s 2.

What damage vou1El the vater surge" through. the re1Ief, valve discharge piping and.'.

qucnch tank cause?

To dati, Nuclear Service h:s not notified our op'erating plants 'to chen~ge HPI policy consistent with Referr.ecs 1 and 2 because of our abo've-stated ques: ions.

Yeti the references suggest the posribility of uncovering.the core if prescnt EPI policy is

~

sontinued.

~

Ce requnu t that In tegration. resolve the issue of how the.HP.I.sys.te,n. sh. o. uld. be. used.

c Me are available to.hcip as needed.

,0

.C

.U $.*l & A c

D. F; llallman - '

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feb c

Attachnents h

j f 8ABCOCK & WILCOX C M ANY

o a r H IL4J T I O N 4 p _g _ 4 Q j

POWER,GEliERAT10H GROUP

'ESPONSE-REO'D FROM A//

DISTRIBUTI0tl APPROVED f

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~V rca G.T. FAIRBURN, SERVICE l'ANAGER J J.8d-ms 443.s File No.

T 3. s r Cust.

or Ref.

DPC, MET ED, FPC,' AP&L,'SMUD, & TECO Date Subj.

SUPPLEllENTARY OPERATING INSTRUCTIONS FOR HPI SYSTEM APRIL 4, 1979 j

,u,,.,,..,.....,...................u...,.

Mt ??

DISTRIBUTION JD ccjm:ss:en

W:::c ::a!:tir.-

V L'ATEf

./d..~M.j.8.1 CD RUSSELL RC LUKEN v.n srss.._.. _._ _.. _ _,,

[ JANIS FAIRBURN The following information has been reviewed and approved for transmittal to your customer.

Please advise your customer by tel' econ 'that this is being forwarded and then telecopy information.

'Although details of the causes and course' of ' events of the incident at Metropolitan Edison's TMI-2 plant on March 28, 1979 are still being developed, it appears that the incident was initiated by a loss-of-main feedwater flow (LOFW) and that a distinguishing characteristic of this transient compared to other previous LOFW transients was the securing o'f the High Pressure Injection (HPI) system. fC'nsequently, o

all operating plants are advised to implement the following immediately:

If the HPI system has actuated because' of low pressure condition, it must remain in operation until either:

1.

th LPl punps are in operation and flowing at a rate in excess of 1000 gpm.each and the situation has been stable for 20 min-utes.

OR 2.

The HPI system has been in operation for 20 minutes and all hot and

'n cold leg temperatures are at least 50 belog the saturation temper-ature for the existing RCS pressure.

If 50 subcooling cannot be maintained, the HPI shall be reactivated.

If th5 HPI system has been activated and if RC pumps are in operation, at least one RCP pump per loop should be maintained."

REVIEWED FOR ACCURACY GTF/hh j,

kl. 'w/[./ /.!WDATE: Yf f'//

6 Jf[p cc: GJ Brazill US Delicate ENGINEERING

< JJ -? l..[

DAThp.{4/y-

"Y JH Taylor XR Ellison NUCLEAR SERVICE:

-M CE Mahaney JR Bohart EJ Domaleski JA Lind' MM

^

'W crich PL Pittman

& % gk/

Cet. tral Files -

, jal3COCh &k.COX mer cencuen cicup if, P.o. Scz 12CO. Lynchburg. V3. 24505 Tefephene: (804) 3S4.s111, April 4, 1979 TMI-79-47 Mr. G. P. Miller

[

Station Superintendent Metropolitan Edison Company P.O. Box 480

~

~

Middletown, PA 17057

Subject:

Three Mile Island Ouclear Generating Statiion - Unit 1 TMI-2 Loss of Feedwater Transient

Dear Mr. Miller:

Although details of the causes and' course of events of the incident at Metropolitan Edison's THI-2 plant on March 28, 197.9 are still being

  • developed, it appears that the incident was initiated by a loss-of-main feedwater flow (LOFU) and that' a dist.inguishing characteristic of this transient compared to other previous LOFW transients was the securing of the High Pressure Injection (HPI) system.

Consequently, all operating

~

plants are advised to implement the following innediately:

If the HPI system has actuated because of low pressure condition, it must remain in operation until eith'er:

l '.

Both LPI pumps are in operation and flowing at a / ate in excess o.f 1000 GPM each and the situation has been stable for 20 minutes.

og e

2.

TheHPIsystemhasbeeninoperationforg0minutesandallhot and cold leg temperatures are at least 50 below the saturation temperature for the existing RCS pressure.

If 500 subcooling can-not be maintained, the HPI shall b,e reactivated, kf. the HPI system has been activatdd and if RC pumps are in operation, at least one RCP pump per loop should be maintained.

This information supplements that previously transmitted..If you have any questions regarding this advisory, please advise.

Very truly yours,

_A. J. 2L '

G. T. Fairburn.

Service Manager GTF/hh cc:

RM Klingaman bcc:

JD Phinney JF Hilbish RL Pittman

' LL Lawyer TM Dixens GM Olds JL Seelinger HA Bailey CR Montgomery Record Ctr. N55-5 T1.2 LC Rogers SL Saith he Batcock & Wiker Company / Es-

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R. E. HAM /G. T. FAIRBURN, NUCLEAR SER;YpCEONSE RE ID FROM1 c. 7 ' 1;y h YED _]

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7 G. J.

BRAZILL, PLANT INTE RATION

/

' M "j File No.

Cust.

or Ref.

DPC, MET ED, FPC, APSL, SMUD, TECo T3.35 Date S u bj.

SUPPLEMENTARY OPERATING INSTRUCTIONS FOR.HPI APRIL 17, 1979

,...................................~....

RE:

G. T. FAIRBURN TO DISTRIBUTION, SAME SUBJECT, T3.35, APRIL 4,-1979.

THE OPERATING INSTRUCTIONS, GIVEN IN THE ABOVE REFERENCE, FOR OPERATOR ACTION TO OVERRIDE THE ENGINEERING SAFETY FEATURES ACTUATION SYSTEM AND TERMINATE HPI HAVE BEEN REVISED.

~~

THIS. REVISION (ATTACHED) ALLOWS THE OPERATOR AN ALTERNATIVE

.TO THE 20 MINUTE OPERABILITY PERIOD, UNDER CERTAIN CONDITIONS, TO PREC'LUDE THE PRESSURIZER FROM GOING SOLID.

PLEASE REVIEW A

AND TRANSMIT THESE REVISED INSTRUCTIONS TO ALL AFFECTED B5W CUSTOMERS.

= :.

....!.......i..--------

~

~

~

I-- Ti' ENGI'NEERING DEPARTMENT REVIEW 5 APPROVAL e S M Ouaa DATE

/7 7f

../[.~cAE./ 1 N--

j 3 UM;.DUNN, UNIT MANAGER, ECCS 77

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J E;;71~.E. A.

WOMACK, YXNAGER, PLMT DESIGN

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DATE

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HIVIEWED FOR. ACCURACY-I D..

L ROY,. FM., ENGINEERISG UEFT.

o h:GiNEERING:

g DATE; /7 d.,..g DATE D.-,N

. mq SGavlCE:4 DA7 E.

FINNIN, LICENSING

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C :_E W :'E F~~

75! 2 2 I ' El I'- - ~

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Attach h cc:

L.

R..Carti, D.

F.

Hallman E. 'W. Swanson B. M.'Dunn R.

E. Kosiha J. H. Taylor N.

S.

Elliott D.

W.

Labelle R.

W. Winks R. J. Finnin D. 11. RoY E. A. Womack e

,, ~.

O O

'/

SUPPLEMENTAL OPERATING INSTRUCTIONS

~

i FOR HPI SYSTDI OPERATION T

ALTHOUGH DETAILS OF THE CAUSES AND COURSE O'F EVENTS OF THE AT MBTROPOLITAN EDISON'S TMI-2 PLANT ON MARCH 28, 1979 ARE STILL BEING DEVELOPED, IT APPEARS THAT-THE INCIDENT WAS INITI ATED BY A LOSS-OF-MAIN FEEDWATER FLOW (LOFW) AND.THAT A DISTINGUISHING CHARACTERISTIC OF THIS TRANSIENT COMPARED TO OTHER PREVIOUS TRANSIENTS WAS THE SECURING OF THE HIGH PRESSURE INJECTION

. CONSEQUENTLY, ALL OPERATING PLANTS ARE ADVISED TO IMPLE-SYSTEM.

MENT THE FOLLOWING DDfEDIATELY:

IF THE HPI SYSTEM HAS ACTUATED BECAUSE OF LOW PRESSURE CONDITION, IT MUST REM h IN OPERATION UNTIL.ONE OF THE FOLLOWING CRI IS SATISFIED:

_ g..,

BOTH LPI PUMPS ARE IN OPERATION 3ND FLONING AT A RATE IN 1

EXCESS OF 1000 GPM EACH AND THE SITUATION HAS BEEN STABLE FOR 20 MINUTES.

' ' - -- ~~" m ;.

- _ ~

OR ~ ~

THE HPI SYSTEM HAS BEEN IN OPERATION FOR 20 MINUTES AND 2.

ALL HOT AND COLD LEG TEMPERATURES ARE AT LEAST 50 BELOW THE SATURATION TEMPERATURE FOR THE EXISTING RCS PRESSURE.

IF 50 SUBC00 LING CANNOT BE. MAINTAINED, THE HPI SHALL BE REACTIVATED.

,1 og 3.'

kLL ikOT AND COLD LEG TEMPERATURES ARE AT LEAST 50 BELOW THE SATURATION TEMPERATURE FOR THE EXISTING RCS PRESSURE, AT"LEAST ONE RC PUMP IN EACH L00P IS RUNNING, AND THE ACTION IS NECESSARY TO PREVENT THE INDICATED PRESSURIZER LEVEL FROM GO'ING O'FF-SCALE HIGH.

'IF 50 SUBC00 LING CANNOT BE MAINTAINED,

~

~

THE HPI SHALL BE REACTIVATED.

...s..

F THE ilPI SYSTEM llAS BEEN ACTIVATED AND IF RC PUMPS ARE IN E

OPERATION, AT LEAST ONE RCP PUMP PER LOOP SHOULD BE MAINTAINED.

e

. g m..m y. m _ __

-=n.

.h

.(9 O.

Babcock &Wilcox Fewer Generation Grcup.

1 P.o.,8cx 1260. LynchburE, va. 245C5 Telephone: (804) 384-5111

. April 18,1979

,THI,-79-56 Mr. G. P. Miller.

N

~

Station Superintendent Metropolitan Edison Company P.O. Box 480 Middletown, PA 17057

Subject:

Three. Mile Island Nuclear Generating Station - Unit 1 HPI - Operating Instructions

, Letter.,GT.FairburntoGPMilier,TMI,-79-47' dated 4/4/79

Reference:

~

,[

Dear Mr. Miller:

The operating instructions, given in the above refers / ce, for operator action to override the engineering safety features actuation system

~

and terminate HPI have been revised.

This r'evision (attached) allows the operator an alternative to the 20 minute operability period, -

- glll1..~

under certain conditions, to preclude the pressurizer from going solid.,

\\

This information supplements that previously transmitted.

If you have 2ny questions regarding this advisory, please advise.

Yery truly yours, f

~

..b Ojd----

G. T. Fairburn Service Manager' GTF/hh

, Attachment cc: w/ attachment RM Klingaman JF Hilbish LL Lawyer JL Seelinger CR Montgomery LC Rogers SL Smith bec: GM Olds JD Phinney Record Ctr. NSS-5/T1.2

..e O

e N4n@mrtson /1 Rarablesing Tm7

U V:

SUPPLEMENTAL OPERATING INSTRUCTIONS FOR HPI SYSTEM OPERATION REY. 01 - 4/17/79 Although details of the causes and course of events of the incident at

}btropolitan Edison's TMI-2 plant on Ibrch 28, 1979 are still being developed, it appears that the incident was initiated by a loss-of-main feedwater flow (LOFW) and that a distinguishing characteristic of this transient compared to other previous LOFW transients was the securing of the high pressure injection (HPI) system.

Consequently, all operating plants are advised to implement the following immediately:

If the HPI system has actuated because of low pressure condition, it must remain in operation until one of the following criteria is satis-fied:

1.

Both LPI pumps are in operation and flowing.at a rate in excess of 1000 gpm cach and the situation has been stable for 20 minutes.

OR The HPI system has been'in operation for 30 minutes and all hot g

2.

and cold leg temperatures are at least 50 belowghesaturation temperature for the existing RCS pressure.

If 50 subcooling-cannot be maintained, the HPI shall be reactivated.

j OR 3.

All het and cold leg temperatures are at least 50 below the saturation temperature for the existing RCS pressure, at least one RC pump in each loop is running, and the action is necessary to prevent tge indicated pressurizer level from going.off-scale high.

If 50 subcooling cannot be maintained, the HPI shall be reactivated.

If the HPI system has been activated and if RC pumps are in operation, l

.at least one RC pump per loop should be maintained.

l i

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.. o e u -...i i l pod 52 GENERAT1011 GROUP

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Dfstribution

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T. Willse, Licensing (2208)

./h, ws.63.c File No.

Cust.

~

Toledo or Ref.T4. 2.3 Date Su bj.

Loss of Pressurizer' Level Indication March 9, 1979

m..-...................._,_...s..

Distribution:

R. L. Reed' R. W. Winks

~

R.* C.

Luken L. R. Cartin J. T. Janis E. A. Womack G. T.

Fairburn D. Mars C. D. Russell J. O. Howard J. H. Taylor J. D. Agar E. R. Kane F. R.,Faist A meeting to discuss the loss of press'urizer level ihdication at DB-1 was convened Februz.ry 14, 1979 at the B6W offices.

in Lynchburg.

Those in attendanne were:

pii "lii.

J. E.

Kohler NRC Region III s

s J.

E. Poster NRC Region III.

D. Anderson NRC/OIE/LCVIP Sushil Jain Toledo Edison J.

F. Hilbish Metropolitan Edison R.

A.

Dietrich SMUD M.

D. h"n ir e.

Arkansas J. T.

Enos Arkansas E.

R.

Kane B5W R.

C.

Luken S.

H. Klein F.

R.

Faist B. M.

Dunn

'L.

R.

Cartin R.

W.

Winks J.

T. Willse This meeting was requested by the Region III inspectors.

The purpose cf this meetin was thought to be to discuss the loss of pressurizer.. l evel. adication on all B&W plants. ' The utilities were present to discuss incidences where loss of level indication occurred at their plants.

Mr. Foster of the NRC opened the deeting by. stating that the purpo'se

(

cf this meeting was to investigate an allegation by an SRC inspector that B6W had not responded in a timely manner to resolve the loss cf pressuri er level ihdicat. ion concern at DB-1.

He apologized to the utilities: for his method of requesting information from them; not realizing that the utilities would feel compelled to send

r'epresentatives to this meeting.

Mr. Foster next asked the utilities to respond to the ouestions he had submitted (letter. attached).

The questions were:

.p (1)

What previous experience of loss of pressurizer level have occurred?

(2)

The facility where the event (s) were experienced _

(3)

The dates of occurrence.

(4)

Whether the NRC was informed of the event.

(5)

What evaluation of the event'.was perfo,rmed?

Duke Power and Florida power did-not send a representative to the meeting because they'have not experienced a loss of pressurizer level indication.

Mr. Hilbish stated that TMI t1 had not experienced any loss of pressurizer lev'el indication.. TMI t2 had two such events (4/23/78 6'11/7/78) both of which were reported to the NRC in LER's.

Both of these events were thoroughly evaluated.

Mr. Enos stated that ANO-1 had experienced 2 transients during which pressurizer level indication had been lost.

Neither event had been officially reported to the NRC although their inspectors were aware of both events.

Both events were evaluated by BGW and the ANO safety committee. 'As a result of those evaluations AND believes that loss of pressurizer level indication is only g#

as operational inconvenience and that RC pressuriter is sufficient to determine if the pressurizer has gone " dry P,.

\\.

Mr. Dieterich acknowledged that SMUD has had approximately 38 trips during which loss of level indication occurred on 5 to 10 of those transients. These events were not officially reported to the NRC although their inspectors were aware of the loss of pressurizer

. level indication.

SMUD also had experienc,ed two rapid cooldown transients during which pressur.izer level indication was lost, these~ transients were evaluated and reported to the NRC.

Mr. Jain described the one transient where loss of level indication had occurred at Toledo.

This transient was evaluated and reported to the NRC in an LER.

He further described the discussions that had occurred between Toledo, the NRC, and B5W.

The remainder of the morning was spent discussing the consequences of loss of level indication, the differences between DB-1 and the other B5W plants, and the dual level set point for the steam generator at Toledo.

Mr. Foster, closed the morning meeting b'y thanking the utilities for their cooperation.

He stated that as far as he was concerned loss of press'urizer level indication was merely an operational

  • incony.enience and that the. loss of pressurizer level was not a safety concern.

He was recommending that this issue be closed.

He agreed to send copies of his report to all utilities in attendance.

.=

O e

G e

e

w

'Me's s r s.~ Fe s t er and Koh3 e r spent most of the af ernoon. reviewing the 'Telede ~ccrresponder.ce file per:aining to the overcooling tran-F sient.

As a result of this reviev' and the morning discussions Messrs. Foster and Kohler were convinced that 35h' had responded in a manner consistent with the magnitude of the problem.

Mr. Foster surmarized the days meeting by stating that he believed 35W had been exonerated of the charge that they had not responded in a timely manner, that the loss of pressurizer -level indication was only an operatibdal inconvenience, and that the loss of pressuri2er level was not a safety concern.

The only item that remained open was a review of the DB-1 operating instructions to insure that Toledo was operating.the plant in the manner prescribed by B6W.

Copies of Arkansas, SMUD and Met. Ed. written responses to the NRC questions are attached.

JTW/fw Attachment 5

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TELEPHONE :15 - 929-2501 Op pt:E:Ox ! c2 RI ADINC rErir:SYt.v ANIA 1M3 Feb'ruary 8,1979 GQL 0200

.c. Joe.1 T. Janis Service Manager 2.abcock & Wilco-7.0, 3cx 1260 Lynchburg, Virginia 24505

Dear Mr. Jants:

~

~hree Mile Island Nuclear 'S tation, Unit 2 (THI-2)

Loss of Pressurizer Level Indication

.r In response to your letter of Feb uary '2,1979 concerning lo'ss of pressurizer,-

Ic24.1 indication, the f olloe.ng a.ns. vers to th.e questions ref erenced in the KEC

' letter of January 31, 1979 are provided:

~

Tvo o::urrences have taken place folloving rete::r trips chich resel:ed 1.

fii; 1., loss of pressuri a level indica:icn.

g 2.

Metropolitan Ediscn Conrany

~ 1and, i.* nit 2 3.

Three Mile 3

4.

a.

1.pril 23, 1978 b.

T.ovember 7, ic78 5.

les - a.

Inspection Repor: 76-17, dared May 31, 1978 e

LII 7 8--033/17, dared May 8, 1978 Special Repcrt, dated July 24, 1978 u.

.E, Inspection Reper: 7 8-13, d ated Nove=ber 30, 1978

~

special R.cport 75-65/99I, dated Jamuary 30, 1979 E '.

Folloeing each of these vo even s an evaluarien uns made to dete._ine

~

the effec on the Reactor Coolant Syste=.

a.

In the April 23, 1978 event, although the pressurizer l'evel indica:icn had gone belov =cro, evaluations de=onstrate that the ccre remained covered.throughout the ::ansien:.

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ga. 7- -.

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Ir. the Neve=ter.7 1975 eve:. zithough the p esrur'::er level indicztien had Bone belov zerc. a vole =e of S.'.C tzllcas of veter re=ai sed in the pressur'.:er.

The core re=zined covered through-out the transient.

No events concerning loss of pressurize level indication have occurred et Tnrc.e Mile Island Unit 1 during operation.

J.

currently stheduled,. I vill attend the! strategy.necting en Tuesday, February 13, 1979 at I.ynchbu rg,

t..

Sincerely,

  • l.

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Y. Ei1bish n'... "...

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$Upervisor-Generation lice sing 5f.

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S' b seno Mu: lear Ceratirs-S*::tci::c, bit.5ia.1 1~zy zi Fress&r Level Indicaticd

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..r....Sincemly yours,

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A=> KANSAS P ~3 W E F. R L. G H T COMPANY a

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Pehr ua r.y 20, 1579 oONAL.D A. AUs I cH

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N6C 8770 u..

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..g Mr. Ray Luken, Senite P.anager c

BEbcock L Milcox C ptrY Huclear Power Generation Division ~

P. O. Box 1260

~

Lynchburc, Virginia 24505 1:.

Subject:

Pressuri:er Level Indication-W.

(File:

3740)

Gentiemen:

Tne followine is previded ir. response 'to your letter of February 2,1979

., j

.J-'

(AND-79-13).

15%,

Item 1:

Enat previcus experiences of loss of pressurizer Tevel have occurred?

s ANO-I has never lest pressurizer leYe1 due to nomai

Response

operati:nal transier.ts.

We have, or. a few occasions, lost pressurizer ine cation; however,. pressurizer level was reaintained in each instance.

It m 2.

The name of the involved utility for these events.

Response

Arkansas.Comr an'd Light Ccxnpany.

+.

8

... ~

It s 3.

The facility @.ere the event (s) are experienced.

Response

Arkansas Nuclear Cne '- Unit One.

~

Iten 4.

Tne dates of occurrence.

~ Soecific dates are not readily avaiT.able.

Bey were

~

Response

in late IS74 and 1E75.

Item 5.

Paether 'the hT. wis informed of the event.

fr ra*.iy infor.ned, hacer at least two m.~~

Response

NT4 wa: nn:

c.epinn P. inspectors were aware of ::he occurrences.

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TRITIU?f LEVELS IN GROUNDWATER (pCi/t)

WELL 1/24 1/25 2/19 2/25 2/29 3/7 3/11 3/26 3/27 3/28 4/1 4/2 4/3 1

200190 990190 1650+

2 15301150 (Recount 250011301 1550210(y 1 01140 from 2/25) 0180 300380 3

290190 6601100 240190 4

170170 200180 5

290 70 380180 300 70 t

6 280~*

310180 7

100t80 300 80 8

160180 B70 90 OTilER NUCI.IDE DETECTED 1 Co 12.814.6 pCi/t.

2 Co 10.6 5.1 pCi/t 3 Co 11.517.0 pC1/1

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_q TRITIL?1 LEVELS IN GROUNDWATER (pCi/1)

Well 4/9 Teledyne 4/9 RMC Cor: ment s 1

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.v STATUS OF GR0UtiDWATER M0fi!TORING AT TMI t

The licensee continues to sample and analyze groundwater from the eight new Samples continue to show only background levels constructed monitoring wells.

These levels r

of tritium, except for the anomolously hig.h levels from well MW-2.

1500-2500 pci/1, which is well below drinking remain relatively constant at about In addition, HRC is obtaining soil and water samples and will i

water standards.

l f,

independently assess the contaminant levels.

14,1980, representatives of Met Ed, the State, and NRC reviewed a l

On April

. Installation for an expanded sampling system to identify the source of the tritium.

of new observation wells will begin on April 21, 1980.

fiRC will continue to regularly monitor the progress on this investigation.

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6.2 SURFACE WATER HYDROLOGY The major stream affected by liquid discharges is the Susquehanna River, having a drainage area at the site of approximately 25,000 square miles.

The Susquehanna has a total drainage area of 27,400 square miles where it enters the Chesapeake Bay.

The main tributaries in the vicinity of the site are the following:

Stream Drainage Area Average Flow (M ')

Conodoguinet Creek 483 sq. mi.

57t W cfsa Yellow Breeches Creek 227 sq. mi.

2?c k26 cfsa Swatara (, reek 567 sq. mi.

7~ h66 cfse Conewago Creek (West) 510 sq. mi.

syv hie cfso The Juniata River enters the Susquehanna River about 25 miles upstream from the site.

Its drainage area is about 3,426 square miles and its

<:%S y 3e a average flow isy cfsa.

The plant site on Three Mile Island is located approximately 11 river miles downstream from Harrisburg gaging station, which has a continuous period of record since 1890. The drainage area of the Susquehanna River at the Harrisburg gage is 24,100 square miles. The average river flow 1v.cc c per square mile at Harrisburg is MR cfsy. The data for the Harrisburg gage are assumed to be applicable to the site, which har e" estimated W

drainag arca J 25,00 woe. m mils.

y,y The Susquehanna River is-rather extreme-in-Reflow characteristics, as i

o n..,

ts-evittent in the following summary of recorded data at Harrisburg:

Minimum daily flow 1,700 cfs Average annual discharge 34,000 cfs Ayerage e.mner nor enunce wie An cfw Mean annual flood 300,000 cfs Maximum flood of record (1972) 1,020,000 cfs *

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. No large dams or reservoirs exist immediately upstream from the site. The Corps of Engineers has constructed a new dam for flood control on the Raystown Branch of the Juniata River. The Project is also used for low-l flow augmentation and for recreation. For low flow control, the project increases depeiidable flow at the Raystown dam site to 480 cfs. This benefit will also be felt at the plant site.

A pump storage facility consisting of two reservoirs and dams is proposed for completion in 1983-84 on Stony Creek, approximately 13 miles northeast of Harrisburg and upstream of Three Mile Island. The project will afford some degree of low flow augmentation for the Susquehanna River.

9 Low flow studies of the Susquehanna River were conducted using data from the Harrisburg and Marietta gaging stations as recorded by the USGS. The Harrisburg gage has maintained continuous records since 1890, and Marietta since 1931.

Figure 1 shows a flow-duration curve for the Susquehanna River at Harrisburg, based upon daily flow data. The minimum flow of 1600 cfs occurred on November 29, 1930 as the result of an ice blockage of the river. The minimum daily discharge since the construction of a sanitary dam downstream from the water filtration plant was 1,700 cfs on September 28, 1964. The average yearly discharge at Harrisburg is about 34,000 cfs.

The following tabulation summarizes the percent of time the flow is equal to, or less than the average yearly discharge:

l I

pl@. 4

, Flow in cfs Percent of Time 2,000' Negligible 3,000 2

4,000 4

5,000 10 6,000 13 7,000 17 l

8,000 20 9,000 24 10,000 27 20,000

~50 34,000 average flow 69 Figure 2 shows a minimum flow summary of mean monthly flows for the Susquehanna River at Harrisburg. The data show mean monthly flows by.

months for recurrence intervals of 2, 5, 10, 20 and 50 years. The curves 9.:o !;<. w { M 2 '

on Figure 2 were developed,from mean monthly flow data for the period of record from 1890 to 1967.

It will be noted on Figure 2 that

}

l characteristically the low flow occurs in the late summer and fall, and that the minimum mean monthly flow of record, in general, falls-below j

the 50-year curve.

Extrapolation of the individual monthly curves for August through December produces the following mean monthly flows for the recurrence interval of once in 100 years:

Month 100 Year Low Flow August 2000 cfs September 1700 cfs October 1250 cfs November 1700 cfs-December 2600 cfs The minimum flow duration summary is presented in Figure 3 which shows not only the minimum daily flows, but also their probable frequency and duration.

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A flow of /Gco cfs, corresponding to [g&'*

0 e'g was selected as the river flow to be used to determine dilution factors-for the dis-charged water from EPICOR.

If flow in the. river dropped below this infrequent flow rate, no water would be released from 'the plant.

At the head of TMI and :!;u T Shelley's Island, the flow of the Susquehanna is split into several segments. Based on work performed by I

the licensee (Reference /), the amount of water flowing past the discharge point (in the middle channel between TMI and Shelley's Island) will be approximately ?I % of the total river flow.

Therefore, a flow of +'do cfs was used to compute resultant dilution factors in the river at various locations, even though the total flow of the river would be effective in diluting the discharged waste water efter the flow had passed over and through the turbines at York Haven Dam.

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C 1 ILCD LFS SUSCUEHANNA RIVER AT ilARRlSBURG, PA, MINivUM DAILY FLOY/ DURATION

SUMMARY

THREE '.'.!LE ! ELAND NUCLE AR STATION SUPPLE"ENT FOR UNIT 2 h

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FIGURN

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i JAN FEB Wit AFR MAY ltN JUL AUG SEP OCT MCV DEC 1AN SUSCUEHANNA RIVER AT HARRISBURG, PA.

MEAN MONTHLY FLOW

SUMMARY

THREE MILE ISLAND NUCLEAR STATION SUPPLEMENT FOR UNIT 2 M.g h g.

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6.3 SURFACE WATER USES The river and the streams in the vicinity are presently used for water supplies, both public and industrial, power generation, boating, fishing, and recreation. Sport fishing is done in all streams in the genet al area of the site; however, there is no comercial fishing. Eleven down-stream surface water users have been identified within 50 miles of the,

site. The nearest user of surface water is five miles downstream.

Approximately 1155 cfs is withdrawn from the river at this location by the Brunner Island steam-electric generating station; a portion of the If

%(M3)

b withdrawal is used as potable water.

Figure the locations E

of downstream surface water users.

The following summarizes the available information on water supplies

~

downstream from TMI for a distance of 50 miles.

The consumers include,Ti Qln,-

,:d public water supplies, industries, and utilities.

fs/

d?&(ps :..

a.

A wholly owned subsidiary of Met-Ed, York Haven Power Company, owns : 'E.

p a hydroelectric generating station operated by Met-Ed at York Haven with a total installed capacity of 20,000 kw. A dam across the h,

Susquehanna River impounds 8,000 acre-ft of water for generation, air [

conditioning, cooling and fire protection.

Potable water is obtained from two wells.

~;. /

b.

The Pennsylvania Supply Company takes 2,200 gpm per nine hour day

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if from the mouth of Conewago Creek for sand and gravel processing, 7x M

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which is discharged into the Susquehanna River after clarification.,y(y

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PP&L owns and operates Brunner Island, a steam-electric generating c.

station on the west shore of the Susquehanna River five miles down-stream from the nuclear station. With a generating capacity of 1415 MW, the station utilizes 1,155 cfs of river water for the circulating water system and ash removal, which is returned to the river without reconcentration. River water for potable and cycle makeup demineralizer requirements is treated prior to use.

d.

The Wrightsville Water Supply Company has a public water supply intake on the Susquehanna River 16-1/4 miles downstream from the I

l nuclear station.

The intake is utilized as a sumer reserve supply with ccg6 treatment facilities provided in the system.

The borough of Columbia takes an average supply of two million gallons e.

i per day from the Susquehanna River from an intake located 16-3/4

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M' miles downstream from the nuclear station.

The water receives e m ef,g

_ A ;nete treatment prior to distribution.

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The Safe Harbor Water Power Corporation owns and operates a hydro-electric generating station on the Susquehanna River about 27-1/4 miles downstream from the nuclear station.

The dam across the river impounds 92,000 acre-ft for power generating purposes. Water for a public water supply system for the village of Safe Harbor is withdrawn from the reservoir at a rate of 25,000 gallons per day and receives complete treatment.

A p.

A public water supply system serves the village of Holtwood on the east side of the Susquehanna River 34-3/4 miles downstream from the nuclear station, at Holtwood Hydroelectric Station. Approximately J

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_ 22,000 gallons per day is withdrawn from the 19,300 acre-ft 1101twood Reservoir and treated prior to distribution.

./.,h. The Muddy Run Pumped Storage generating station is located 38 miles downstream from the nuclear station.

It is a remotely controlled 800 MW capacity station, operating between an upper reservoir and Conewingo Reservoir. River water is used for fire protection.

Potable water is supplied by deep wells.

4 -M Peach Bottom Nuclear Generating Station is located along the west l

bank of the Susquehanna River about 41 miles downstream from Three Mile Island. The initial unit, rated at 40 MWe, which was part of the AEC Power Reactor Demonstration Program, withdraws 90 cfs from the river for cooling purposes. Peach Bottom Unit 1 has filed for

\\j decommissioning. Two additional nuclear units, each rated at 1,000 t1We, are presently operating and withdraw a total of 3,450 cfs from the river for cooling purposes.

j J".

The city of Baltimore has an intake on the river which draws water from Conewingo Reservoir. The intake is located about 49 miles downstream from Three Mile Island.

Baltimore is permitted to with-draw up to 250 MGD when the river flow exceeds 5,000 cfs, but is limited to 65 MGD at lower river flow. Two water treatment plants provide ~ r';t; treatment.

'u p g. Philadelphia Electric Company owns and operates a hydroelectric generating station at Conewingo Dam which impounds 321,500 acre-ft in Conewingo Reservoir. The facility has a capacity of 513,000 kw, 4

e-

fA 9

, and is located 50 miles downstream from Three Mile Island.

Potable water supply is obtained from the reservoir to supply the station and Conewingo Village. C;p';t;1reatment is provided for an average

'd supply of 12,000 gallons per day.

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7,3 DILUTIO!! AtlD DISPERSION OF LIQUID EFFLUENTS Irl THE SUSQUEHAfit!A RIVER The liquid waste flow of 10 gpm from EPICOR will first be mixed in the system with a flow of 38,000 gpm (84 cfs). The water will then be discharged to the i

Susquehanna River through the normal blowdown discharge structure.

When the waste flow of 10 gpm is mixed with the normal discharge flow of 38,000 gpm, it can be seen that the waste undergoes immediate dilution by a factor of 3800 prior to release to the river.

)

After release to the Susquehanna River, the flow of 38,000 gpm will be further

~

diluted by the river. The amount of dilution received depends primarily upon the river flow at the time of discharge.

For the purposes of computing a conservative dilution factor, a river flow of 1600 cfs was selected (see Section 6.2).

To account for incomplete mixing with theentireriver,themiddlechanneldischargeof4b0cfs(seeSection6.2)was l

selected.

This is the effective flow to be mixed with the pollutant discharge I

for the nearest water use location at York Haven Dam. The resultant dilution factor then is simply the river flow (400 cfs) divided by.the pollutant flow i

10 o

( ^ 0 (post -fs),or d ighti; m e th r t A dilution factor of / was used to compute the concentrations shown in Table

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