ML19322A610
| ML19322A610 | |
| Person / Time | |
|---|---|
| Site: | Oconee  |
| Issue date: | 03/11/1971 |
| From: | Seidle W US ATOMIC ENERGY COMMISSION (AEC) |
| To: | James O'Reilly US ATOMIC ENERGY COMMISSION (AEC) |
| Shared Package | |
| ML19322A611 | List: |
| References | |
| NUDOCS 7911210685 | |
| Download: ML19322A610 (2) | |
Text
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UNITED STATES ATOMIC ENERGY COMMISSION l.
i civis:ON OF COMPLIANCE REGloN ll - sulTE 818
/
@g 230 PEACHTREE STREET. NORTHWEST I48 Tatarssoser 526-4537 AT LA NT.. G E OR G I A 30303 March 11, 1971 J. P. O'Reilly, Chief, Peactor Testing and Operr.tions Eranch Division of Compliance, Headquarters DUKE POWER COMPANY (OCONEE 1), LICENSE NO. CPPR-33, DOCKET NO. 50-269 The attached report of an inspection of the subject facility by our inspector en January 25 and February 10-12, 1971, is forwarded for infor-mation. No items of nonconformance vere detected during the inspection.
On February 11-12, our inspector acce=panied representatives from DR, DEL and DRS en an inspection of the installed electrical and instrumentation systems related to safety. The inspection did not reveal any deficiencies of major significance. Some six items that were considered to warrant corrective action are discussed in Section F.1 and have been added to the Outstanding Items List (Exhibit A).
Most of these items had been previously identified during previous Region II inspections.
In reviewing the containment leak rate test procedure, our inspector noted that the licensee did not plan to conduct a controlled leak rate test after completien of the full accident pressure test.
Instead, this test vill be performed after the ccepletion of the leak test conducted at 50" of the maximum accident pressure. You will note that we have urged the licensee to give consideration to also performing a controlled leak test at the con-clusion of the maximum nccident pressure test. We feel confident that the test in question vill be incorporated in the containment leak rate test procedure. This vill be a follovup item for our next inspection.
The construction progress is very slow and it is most unlikely that they will meet their initial fuel leading date scheduled for July 1971. We feel that late Septe=ber 1971 is a more realistic date.
The test program is just getting underway, primarily because most of the piping systems have not been ecmpleted.
.[
W.C.SeidlN Senior Reactor Inspector C0:II:WCS
Enclosure:
CO Rpt. No. 50-269/71-2
($*urphy) 7911210 bb
Q J. P. O'Reilly March 11, 1971 cc v/ encl:
E. G. Case, DRS (3)
P. A. Morris, DRL R. S. Boyd, DEL (2)
R. C. DeYoung, DRL (2)
D. J. Skovholt, DRL (3)
P. W. Howe, DRL (2)
A. Giambusso, CO L. Kornblith, Jr., C0 R. H. Engelken, C0 J. B. Henderson, C0 R. W. Kirkman, CO:I B. H. Grier, CO:III J. W. Flora, CO:IV R. W. Smith, CO :V IG Files