ML19322A588
| ML19322A588 | |
| Person / Time | |
|---|---|
| Site: | Oconee  |
| Issue date: | 06/28/1971 |
| From: | Seidle W US ATOMIC ENERGY COMMISSION (AEC) |
| To: | James O'Reilly US ATOMIC ENERGY COMMISSION (AEC) |
| Shared Package | |
| ML19322A589 | List: |
| References | |
| NUDOCS 7911210668 | |
| Download: ML19322A588 (2) | |
Text
e UNITED STA ~
Q ATOMIC ENERGY COMMISSION r
p 1
t civisloN OF COMPLlANCE
.l REGION ll - $UITE S18 s
230 PE ACHTREE STREET, N oR T H W E ST D
Tmmi 3M AT LA NT A, GEORGI A 30303 h.a 2s, l?71 J. P. O'Reilly, Chiaf, ieset:r Testing and C;erations Branch (2)
Division of Complianca, Headquar:ere DUKE POWER CCMP.55.' (00C523 1), * ~ 0ZN3Z.%. CIII-33, DCCKII NO. 50-269 The attached repcrt of an inspection cf the atoject facility by our inspectors on May 4-7, 1971, la fonarded for infermation. Two items of nonconformance with the 18 CA Critsria were detected during the inspection.
One item involved lack of adequate test control (Criterion XI), the other involved inadequate a.udit of tests (Oriterica XVIII). A CDN was issued on May 15, 1971.
Concerning the poly +chyltna trapped in the reacter vessel internala, which was the subj ect of cur Mar:h la,1971 CDN, we consider the licensee's resocase to be umaaeisfacto f and have forwarded this matter to Headquarters fcr resciution.
The licensee's res;<:nse to tn ite=s in our CDN of April 14, 1971, concerning weld rod control and cable trsy fill, was unsatisfactory. Our position regarding these items was ferwarded to Headquartars en May 27, 1971.
In response to Headquarters request, we have discussed the unsatisfactory response items with the licen,ae. S haa agresd to document cernmitments relating to these iteca in s. f;rtheezir.g supple: ental response letter which we anticipate will rascive there items.
With regard to the internal short circuita in the Viking containment electrical penetrations, the probit: appears :o be generic in nature. A recocrnendation that this matter be rafarred to our !e:hr.ical hpport Branch for evaluation was forwarded to ycu by meceran ks on May 13, 1971.
Information relatir.g to damage to core internala from the inadvertent dis-lodging of two dunny fuel e~ ements is diacursed in Section 13 of the Management Interview section. Preliminary infomatica regarding this matter was advanced to you in cur Inquiry hemorandum dated May 3,1971.
A ti P00RDHINAL y ou, wr
6 s
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'J. P. O'Reilly June 28, 1971 We have detected a looseness in the cenduct of pre-ep tests which is causing us concern. Some deficiencies neted which have generated this concern include the failure to document minor changes to procedures, the failure to perform a safety ::m ittee review and evsluatica of tests and data in a tLoely manner and the failure to establish a ecmposite or summary list of deficient and/or ince=plete ita:a. We fael that =cs: of the deficiencies noted are due to inexperience on the part of the Oconee operation staff and improvement shculd occur as experience is gained. We intend to follow this matter closely en subsequant inspections.
Sections H and I identify these pre-op and startup and power ascension tests required by PI 5800 and FI 10C3 that the licensee does not intend to perform at this time. We cay be approaching an impasse with the licensee in conducting these tests.
If, during the next routine inspection, the licensee does not change his position in conducting these tests, then we will forward the matter to Headquarters for action.
The licensee now estimates that initial fuel loading will take place in September 1971. We feel a mere realistic date would be October 1971.
./
d%.-.
W.C.Seid1h CO:II:WCS Senior Reactor Inspector
Enclosure:
CO Rpt. No. 50-269/71-3 (Murphy) cc w/ enc 1:
E. G. Case, DR3 (3)
P. A. Morris, DRL R. S. Boyd, DRL (2)
R. C. DeYoung, DRL (2)
D. J. Skovholt, DRL (3)
P. W. Howe, DRL (2)
A. Giambusso, CO L. Kornblith, Jr., CO R. H. Engelken, CO J. B. Henderson, CO R. W. Kirkman, CC:I B. H. Grier, CO:III J. W. Flora, CO:IV R. W. Smith, CO:V RRP. Files
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