ML20210H852

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Expresses Appreciation for Meeting W/Nrc to Discuss Concerns Re Steam Generators & Possibility of Large Releases,Should Steam Generator Leaks Occur.Questions Raised by B&W-GPU Trial Data Would Not Apply to Unit 1
ML20210H852
Person / Time
Site: Crane  Constellation icon.png
Issue date: 09/19/1986
From: Davenport D
CONCERNED MOTHERS & WOMEN ON TMI
To: Blough A
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
Shared Package
ML20210H826 List:
References
NUDOCS 8609260345
Download: ML20210H852 (7)
v • d • e


Text

_.

TC ept.

c,1986 Allee R. Bloesh, iieactor k'rojects, Sec tion 1 A,

Division of Reactor l'rojecto, 1:RC reg on 1, i

631 Park Avenue, King of l'ruccia, l'enna.

Dear Fr. Blough:

Thankyou and tir. Conto for meeting with hue and Mr. Epstein to discuss concerns I had about steam generators, and their poonible for large releases, should steam generator leaks occur.

Apparently, some of the questions raised by the B&W-GPU trial data would not apply to Uniti since the engineering of the two plants is different in some respects, at least, in referenco to the condener hotwell problem experienced in UnitJP.,

This means there would be less or no, hopefully, liklihood of booster pumps being lost and thus tripping the feedwater system if I understand the mechanics of the hotwell problem enough.

I still do have strong concerns about releases affecting public health and safety that mi ht occur should a steam ube failure, 6

or any-primary to secondary leak of a substantial size occur.

Apparently there are evaluations now in progrese

, what proceedures t

to. follow in th e case of a major steam tube leak.

I would be very intNrestedinobtainib any copics of those 1,whic's might be or might become available.

Also 1 am requesting that the condonuar fr-gau be filtered 8609260345 860919 PDR ADOCK 05000289 H

PDR r

,3 - -

l (2)

'.70uld in Unit 1, as seon as feasible via the llRR Director.

ld not the cost of such a filter be so prohibitive that it cou As we dincussed an of f-cas filter was in the be installed?

l there original PEIS for THI, at least for Unit 2, and I Ice Happily it was added af ter thcTaccident.

was a reason for it.

Unhappily, as per this final accident task force summary due the by GPU, under the direction of R. heaton, among others, for oof-cas for Unit 2 is listed as one of the raajor pathways Leaku 1 ro.n the TI'I Accident, of 1979 Caseous releas s durinr:

d

/ sid e, the B Generator are said to have contaminated the secon ar; The bect of fence exiting through the condenser off-gas exhaust.

is a good de fenso....I would not want to wait untila stoon, tube release to say, a filter would be nico.

PU-Also enclosed with this letter 'are two excerpts from the G t

bout B&ft Trial Record which show one sampling of the B cenera or a d another at seven AM on Day One of the accident............. an Th' occond from the Kunder 2xibits says 2043 the same day.

Leak that the sample also confirmed the Primary to Secondary s

in the B Generator, but does not specify whethet the sample lido sam; '.c was of the generator itself, it is just called a radionuc EV AM had at3 63 microcuries per millileter.

'rfe sauple at 7:

of 1131 illiliter.

I was intere'stingl;' been at 0.491 microcuries per m incorrect in the way I recounted to Mr. Conto,that campiing, f that account.

and Mr. Kunder's penciled in noted on the margin o i t d in I believe what he meant was, could that activity have ex s e of I131, at that timo-, RG d, in the coquence.

the primary side, r

s.

I Finally ericlosed if I can find it would be un account of the 51st day of the accident, during which the plant went to " natural circulation.

i Bothe the A and B Generators are mentioned no being steatted to j

the condenser, B through Turbine Bypecs valves that were 25% open, in l

j other words, the B Generator was put back in use.

Again I would be happier if I knew that the Condenser Off-Gas had been filtered.

I do not feel it would be reasonable to accume that no Iodine or Particulate did r,ut out by that route.

i

Singrely,

[

Deboral Davenport, 1802 flarhet Street,

1 Camp 11111, Penna.

17011 i

1-717-763-9552 l

Member: Concerned i!uthero i

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Relit:f valve MU-R1 is located downstream of the makeup: tank.

.f gassing in the makeup tank probably caused a pressure buildup suf-.

I ficient to lif t MU-R1 (set point 80 psig) which also discharges to ff,j l

f the RC bleed holdup tanks.

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.s The lif ting of relief valves MU-RSA & B is unlikely by.alther of Pressure drops across;both the the above mentioned mechanisms.

l filters and demineralizers would prevent MU-RSA & B (located dovn-The v-stream of the demineralizers) from seeing high pressures.

i higher setpoint of 150 psig for MU-5A & B also supports the con-o clusion that it was MD-R3 which provided the primary relief path.

High pressure in the makeup tank would be relieved by MU-R1, and f" }

h check valves MU-V133 and MU-V107A & B (all located downs MU-RSA & B) would prevent backflow through the letdown line and out

{

~

.]

  • MU-RSA & B.

l tarting 0435 on March 29th the makeup tank was periodically vented t'o the radwaste gas system vent header by opening MU-V13. Exam-y

[6 ination of strip chart recorders shows a strong' repetitive cor-relation between this venting and the increase in radiation levels

~

gg on several area gamma monitors in the auxiliary building and fuel p

It has been concluded by all investigations handling building.

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\\[

that releases associated with venting the makeup tank represent a V

j large fraction cf the total releases on March 29 and 30. ' There is b

no evidence of similar venting activities on March 28th.

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S.

Steam Generator Leak Based on the behavior of steam generator "B",' the operators suspected on March 28 that a primary to secondary leak had oc-

)

I Steam curred, and this was confirmed by subsequent water samples.

i f

generator "B", af ter being isolated at 0527, was reactivated at Strip. chart recorders (HP-UR-3236-CE 7) indicate a gaseous 0645.

rdesse from-the condenseT vacuum pump _ exhaust beginning 'at E~

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approximately O_700 with a rapid increase in activity.

  • The_ dis-f, charge of the vacuum pumps bypasses the - Auxiliary-Building filters i

~

diid is' routed-directly~ to~the stat' ion vent. Steam generator "B"

~

~ '

The count rate on was reisolatedT0704Taiid remained isolated.

the exhaust monitor peaked at 0715, then decreased and stabilized by about 0830.

Attempts to quantify the releases from this pathway were not Based on the available information, however, totally succesnful.

the total releuces from the secondary system were believed to be substantially le ss than those via other pathways.'

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he :retator

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vith.25ergencT U erating Procedur 2202-I.3 to preclude the P

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near reactor coolant saturation te:perature - pressure conditic....

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~ 4-S Q"1 01:20t31 De operator requested the coepu t e r p ria c t he,

r_lecttenatic

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(052 son e.C e*% q f.eliaf Yalve (IC-R72) outle t te=perature-A value of 283.07 w..

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'-".'.'.. 1 '.7, T. a indicated.

34. sed on this teeperature the operator ce ti.aued to

.( 4 ;..t-';25 believe that the El e c t roeta t ic Ra tie f Tal e.

(R C-Rv 2)

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but.

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(MS-V4B and MS-VT5) we re shut. E=ergency Peedvatar 7alves (ET.

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Coola nt Sy s t e rs t o S t earn Ce o e r a t o r l e ak b a s e d on th. large dif-gY 3.-..

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. 5' 'W f arence in stesse pres sure between the rvo S t e a rn Cener cora ane

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.I5 variations o[ll'U and level experienced while c.-.. m.

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con t r o llin g

-[7j 3 Steam Cenerator. A.radionuclide analysis of a saeple fres t !..

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steam Cenerator taken at.0724 supported this belief.

The saep!.

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