ML20141K815

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Forwards Category B Rept Re Util 700616 & 24 Ltrs Re Visual & Dye Penetrant Exams of Outside Surfaces of Several Reactor Vessel Nozzles Mode in Apr-May 1970
ML20141K815
Person / Time
Site: Oyster Creek
Issue date: 07/31/1970
From: Mckinley J
Advisory Committee on Reactor Safeguards
To: Bush S, Stratton W
Advisory Committee on Reactor Safeguards
Shared Package
ML20091A092 List: ... further results
References
FOIA-91-282 NUDOCS 9203250245
Download: ML20141K815 (1)


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July 31, 1970

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QTJ U. E. Stratton, Chairman Oyster Creek ' Subcomittee A. H. Bosh, Vice Chairman, ACKS

, CATECORY B REPORTS - OYSTER CREEK - JELSEY CENTRAL POWER & LIGRT

, COMPANY _ LETTER DATED JUNE 16, 1970 AND DRL LITTER DATED JtTdE 24, 1970 i

Attached is a brief senaary of the information presented in the i subject correspondence. No ACRS actica appears warranted.

These items may be destroyed when you have completed your evaluation f= of this matter.

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l J. C. McKinley Staff Assistant i

Attachments:

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1) Sumary
2) Jersey Central Power & Light Co
Itr 4td June 16, 1070
3) DRL ltr dtd June 24. 1970 i

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Form AEC-318 (Rev,053) us sostanuthf renme artrLism-o-ase4sn , j 9203250245 910807 PDR P d.I A 'n/

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CYttEE CREZK 2graev Central Power & t.faht Cessamv letter dated Juma'In.

1970 presents tha reselts of vional and dys penetreet , .;- -

- examinations of the setside surfaces of several reestery vessel aossles made in April and May 1970. N finet' .*

results were that the south core spray aossle met ASE code requirements, the penetrant indications em the meeth nossle are ir ;omel weld diseures or bot- tears thac occur during wid solidit'ication,and no relevant indicattens were absorted on the other meesles emandmed. . h indies.

tions of defects in the morth core spray mossles were grouad out without exposieg may sensitized stataloss steel or rede:ing the wall thickness below nimise.ma alloweble.

[ Pipe stresses were reviewed and design calculations were l confirmied to be cwrect.

Additional primary system inspections will be made at the first refueling outage or earlier if opportunity arises. ,

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! No ACRS action required.

DRL letter dated June 24. 1970 requests a schematic drawing of the proposed change (No. 2) to the rod withdrawal prohibit function.

l l No ACRS action required.

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