ML19322A613
| ML19322A613 | |
| Person / Time | |
|---|---|
| Site: | Oconee  |
| Issue date: | 02/03/1971 |
| From: | Seidle W US ATOMIC ENERGY COMMISSION (AEC) |
| To: | James O'Reilly US ATOMIC ENERGY COMMISSION (AEC) |
| Shared Package | |
| ML19322A609 | List: |
| References | |
| NUDOCS 7911210687 | |
| Download: ML19322A613 (1) | |
Text
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UNITED STATES ATOMIC ENERGY COMMISSION g
+{
}e DIVISION OF COMPLIANCE REGION 11 - $UITE 818 s
g' 230 PEACHTREE STREET. N OR T H W E ST TsLuosom 526-4537 AT LANT A GEORGI A 30303 February 3,1971 J. P. O'Reilly, Chief, Eeactor Testing and Operations Branch Division of Ccepliance, Headquarters DUKE POWER COPPA7Y (OCONEE 1), LICENSE NO. CPPR-33, DOCKET No. 50-269 The attached report of an inspection of the subject facility by our inspectors on January 5-8, 1971, is forwarded for action. There were no items of nonconformance detected during the inspection.
During our last visit to the Oconee 1 site, the inspector was advised by the licensee that they had experienced several failures with ITE time delay relays located in the safeguards relay cabinet.
(See CO Eeport No.
50-269/70-12, Section F.3.)
The failures were caused by the breakdown of the insulation between the pickup and hold in coils. Our inspector had been advised that Duke would issue an in-house report relating to these relay failures; such a report has not as yet been issued. In that the failure appears to be of a generic type, we recc= mend the matter be re-ferred to our Technical Support Branch for evaluatien.
Please note that the four stainless steel sections of reactor coolant pipe, which had been furnace sensiti::ed during the modification of the system to acec=modate the new primary pu=ps, have been clad on the inside with stain-less steel.
In Section F.1 of CO Report No. 50-269/70-12, our inspector stated ".
the inspector also pointed out examples of safeguards systems cable f'--
different channels which had been routed in the same cenduit or in very close proximity to each other." Our inspector was advised during this inspection that the licensee had since conducted a review of the above item and had determined that in no case was the criterien for separaticn of redundant circuits compromised.
The licensee is still advertising a May 1971 core loading date. We still feel that September 1971 would be a more realistic date.
--_A m
W. C. Seidle C0:II:WCS Senior Peactor Inspector
Enclosure:
cc w/ encl:
C0 Ept. No. 50-269/71-1 A. Giesbusso, C0:EQ (Marchy)
(20)
L. Kornbli'th, Jr., CO:EQ R. H. Engelken, CO:HQ J. 3. Henderson, C0:EQ
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