IR 05000269/1989033
| ML19332E378 | |
| Person / Time | |
|---|---|
| Site: | Oconee  |
| Issue date: | 11/15/1989 |
| From: | Ennis J, Mcguire J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML19332E376 | List: |
| References | |
| 50-269-89-33, 50-270-89-33, 50-287-89-33, NUDOCS 8912070148 | |
| Download: ML19332E378 (3) | |
Text
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. NUCLEAR REGULATORY COMMISSION '
" g . REGION il i i OI . / 101 MARIETTA STREET, N.W.
ATLANTA, GEoRG1 A 30323 < , A.*O p, .. l y m .; r.. .:h j Report Nos.: 50-269/89-33, 50-270/89-33, and 50-287/89-33 l
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Licensee: Duke Power Company-
, F . , 422. South. Church Street " g e Charlotte, NC 28242
. [ Docket'Nos.: 50-269,-50-270, License Nos.: OPR-38, DPR-47, and-k.
and 50-287-
- DPR-55~
, g- . $ Facility-.Name:. Oconee--1, 2,.and 3 ' g In'spection.lond d: 1 September 30,'1989 j Ill/589 Inspector.4 \\' ' J.(K n s,I afeguards Inspector Date Signed ,
- Approved byr
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N J/ f 9- - -D. R. McGuire, Section Chief Vate/ Signed - ' Safeguhrds Section 7~ ' ' Nuclear Materials Safety and Safeguards Branch . Division:of Radiation Safety and Safeguards P SUMMARY-Scope: This.; routine -announced inspection was co'nducted in the areas of physical protection of a shipment of. irradiated reactor fuel.
, 'Results: In the areas inspected, violations or deviations were not identified.
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4 > .- -. t REPORT DETAILS , , i L1.
Persons C'ontacted' , Licensee Employees'
- T. Smith, Radioactive Material Control Supervisor, Oconee Nuclear Station (ONS)
- V. McCormic, Fuel Handling Supervisor, ONS -
' . 0ther. 0'rganizations J. C. Hurt, Driver, Tri-State Motor Transit Co.
T..R. Hensen, Escort, Tri-State Motor Transit Co.
- Attended exit. interview 2;
Physical Protection'of Shipments of Irradiated Fuel (81310) The. inspector, verified that the licensee'had. notified the States of North
- and L South Carolina, the Commonwealth of Virginia, and the Nuclear
< . Regulatory Co'mmission of the shipment. within the required time limits.
The written notification - contained the information required by 10 CFR
- 73;37(f).
The licensee l.. had - al so taken action to provide in-transit .; protection as required by 10 CFR 73.37(d)
The~ shipment consisted of one NLI-1/2 cask containing irradiated reactor f uel '. The cask.was'placed on a flat bed trailer and covered with a metal mesh personnel barrier. Prior:to the shipment's departure, the inspector measured radiation levels at 'the' outer surface of the personnel barrier.
The highest. reading'noted was 1.36 mR/hr beta gamma. Radiation levels in ,the~normally-occupied portion of the tractor were not measurably different . than area background radiation levels.
' - The _ shipment's departure was delayed six hours past the originally ' scheduled time' due to difficulties in decontaminating the cask.
The licensee reported that they had worked essentially around the clock since
receiving the cask to clean it up.
-There was some confusion noted concerning areas along the route requiring - special escorts. Personnel at the site were aware of and had information i concerning one such area in South Carolina, but were not familiar with arrangements made for a second area in Virginia.
The driver and escort knew about the Virginia-escort, but not the area in South Carolina. This fragmentation of information appeared to have been caused by the fact that Duke Power made the South Carolina arrangements, but relied on the shipment receiver to make arrangements in Virginia.
While information concerning both special escorts was known to Duke Power's General Office, l the site was not fully informed.
No violations were identified in this area.
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Exit Interview .. . - An-exit interview was. held on ' September 30, 1989, with those persons denoted in~ paragraph one. The licensee was informed that no violations were identified.
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