ML19319A723
| ML19319A723 | |
| Person / Time | |
|---|---|
| Site: | Oconee  |
| Issue date: | 10/01/1970 |
| From: | Seidle W US ATOMIC ENERGY COMMISSION (AEC) |
| To: | James O'Reilly US ATOMIC ENERGY COMMISSION (AEC) |
| Shared Package | |
| ML19319A724 | List: |
| References | |
| NUDOCS 7911280628 | |
| Download: ML19319A723 (2) | |
Text
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UNITED SfATES J
~g ATOMIC ENERGY COMMISSION
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l DIVistot4 oF CoMPLI AP4CE 7'
?r RCGION 18 - SUIT E 010 e
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N 230 PE ACHTH EE SYHCE T.
N CR T H v. C S T retum $2 6 4 !I 7 gig O AT t ANT A. GEcace A 30303 Oei @er 1, 1970 J. P. O'Ecilly, Chief, Peactor Inspection and Enforcement Eranch Division of Compliance, Headquarters DUKE POWER COMPAM (OCOMEE 1), htCE ME !!0. CPPR-33, DOCKET !!O. 50-209 The attached report of an insiaction of the subject feeility by our inspectors j
on September 14,19[0, is forwarded for infor. nation.
I!o items of ncntonfor -
anee were detected during the inapection.
I During rodification of the prir' q loop piping to accor_r.odate the new Westinghouse pumps, EW - Mt. Vernon detected evidence of microfissures in the stainless steel cladding.
The licensee reported this fi nding to us by telecen on August 20, 1970, and this inforration was advanced to you by our Inquiry L'exorandum dated isugust 21, 1970.
Mr. R. E. Oller, Fegion III, was at the EW - Mt. Verncn shop when we received word of the clad fissure problea end, therefore, we were able to obtain titely information on the action EW is t:tking to analyze the problem. Oller's report on this n.atter is attnehed as Fxhibit B.
Duting this site inspection, our inspector obtained additionel information on EDT results, repair status, and the possible causes for the clad fissures. This information is covered in Section F.
Please note that the licensee has informed our inspector that ill of the remaining primary pipe in Unit 3 will be penetrant tested for the presence of additional fis-We intend to follow the licensee's investi ation of this tatter G
sures.
closely and I have scheduled our Metallurgical En6 neer, U. Potapcvs, to 1
accompnny the principal inspector to the site on the next visit which is tentatively planned for the week of September 28.
Ey then nost, if not a 1, of the NDT results will be available for our review.
Section M discusses a fire in a section of primary loop piping which took th; life of a Duke employee. Preliminary information on this incident was ad-vanced to you by our Inquiry L'emorandum dated August 21, 1970.
A prelitinary investi ation by the licensee indicates no damage to the p*pe.
However, this 6
matter is still being investigated and the results will be documented by Duke in an in-house report. Our inspector will review this item again dur.ing the next inspection.
Baseline inspection of the two steam generator-4 UT revealed defects in the aanpter between the support skirt and the vessel head.
(See Section K.)
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Although the indications are enall, the number of defects exceeds the number 0>
pu28 q
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J. P. O'Reilly October 1, 1970 o
permitted, and the v.att er has been referred to D&W - Lynchburg for resolutic n.
This item will be reviewed by our inspector during the next inspection.
f udits ennducted by Duke and P&W nnd our inspectors' spot che k of UDT reeerds indicate that the UDT requirenents imposed by Table A have been met.
Reactor core loading is now scheduled for early " arch rather than January 1971.
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W.
C. Seidl CO:II:WCS Senior Reactor Tnapector l
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Enclosure:
C0 Rpt. No. 50-269/70-9 (Murphy) cc w/ encl:
E. G. Case, DRS (3)
P. A. Morris, DRL R. S. Boyd, DRL (2)
R. C. DeYoung, DBL (2)
D. J. Skovholt, DBL (3)
P. Howe, DEL (2)
L. Kornblith, Jr., CO REG Files L
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