ML20141K395

Discusses & Provides Comments on Plant Vessel,Including Distortion Measurements & Other Stresses

ML20141K395
Person / Time
Site:	Oyster Creek, Three Mile Island
Issue date:	01/04/1968
From:	Etherington H Advisory Committee on Reactor Safeguards
To:	Fraley R Advisory Committee on Reactor Safeguards
Shared Package
ML20091A092	List: IA-91-282, Forwards Written Statement Submitted by Sp Russo for ECCS Subcommittee Meeting on 770129,for Info.W/O Encl ML20141K026 ML20141K047 ML20141K056 ML20141K063 ML20141K066 ML20141K070 ML20141K076 ML20141K082 ML20141K091 ML20141K095 ML20141K121 ML20141K137 ML20141K141 ML20141K153 ML20141K163 ML20141K175 ML20141K185 ML20141K190 ML20141K359 ML20141K365 ML20141K368 ML20141K372 ML20141K375 ML20141K379 ML20141K382 ML20141K386 ML20141K390 ML20141K395 ML20141K398 ML20141K402 ML20141K406 ML20141K408 ML20141K415 ML20141K418 ML20141K423 ML20141K426 ML20141K432 ML20141K436 ML20141K441 ML20141K618 ML20141K620 ML20141K625 ML20141K626 ML20141K630 ML20141K633 ML20141K635 ML20141K637 ML20141K641 ML20141K643 ... further results
References
FOIA-91-282 NUDOCS 9203190106
Download: ML20141K395 (2)

Text

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To 1. F. Fraley, Remeutin Betratary, Acts  :

/s/ (f 'G-From Barold Etheringto&c*ts n, A Member subjeeti OffTEg CREEK i

l A few more thoughts on the Oyster Creek vessel.

1. ,

Distorties Maesurements. Measurement of the variaties of thia 61e 1.3.

and stub tube 0.D. as a functies of length aan be used to seafirm the proposed stress analysis. We 1.D. measurement should be easily made but the 0.9.

measurement any be more diffievit-the/' values show that the asial unve.

Iemath of the radial displacement is about'3 in., so measuremmate close to the weld should be made et frequent intervals. Out of-rowed measurements should also be made. I anpoet the applicant is making euch measurements en representative tubes, but it is important to somfirm that this will be done while the opportunity still estats.

1. Other stressu . My previous memorand.es (Deeember 20) dioevosed esial btag atreae because this atrese appeara ta be nost affocted by shange la longth e! atub tube. Bendtag shear atrese ese alse sneettened insidentally, and will he developed by the same analysis. Other stresus abould mise be investigated.

l -(a) In my e Arcle calculated esemple, the hoop atresa (aot 31 wen) is actually greater than the bending stress. Ecoevar, this will probably i mot be true in the sht,rt stub tubes with which we appear to be partieu-l larly senaarmed.

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{ (b) The sayummetry of stub tube length in the ester ettste should l saun as set-of-round sendities near the weld, and this seeld predese

a large circumferential bending stress.

! 3. Cerrections to My Memo of Decesber to.1967 (a) There should be af (beta) La freet of all the I's la ths ogmation en p.3. The "B"

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abeeld sise be/f (to distisemish free "B" in the equation en p.3). .-

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, (b) en pese 3, item 6, the last weed should be "slesses" .

instead of " shields".

(e) It was not intended to imply Nt the present Satterne .

emeld here escurred without serrestos - they alanet sertainly esm14 met. There are really N oe goeottene hP[J[;- .

,y g (t) if strees oorrosion eseurred eeder seedittene of g '. s.

sembined essessive stress and Layrepar envireement, are we '

setag to be souplacent about the emeessive strees tf the envireamentet seedition is serrestadt and (ii) ubet will be N rense of sysits thermal stresses in the outer sirste where the thermal sleeve is almost omt l azi6 tent en one sidet I

(iii) is the destga satisfactory for Dyster creek and

! for future reactors.

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