ML20037A352
| ML20037A352 | |
| Person / Time | |
|---|---|
| Site: | Oconee  |
| Issue date: | 07/17/1974 |
| From: | Seidle W US ATOMIC ENERGY COMMISSION (AEC) |
| To: | Thornburg H US ATOMIC ENERGY COMMISSION (AEC) |
| Shared Package | |
| ML20037A350 | List: |
| References | |
| NUDOCS 8001100626 | |
| Download: ML20037A352 (3) | |
Text
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UNITEo STA TES
/ */.. - t ATOMIC ENERGY CCMMISSION h D,. {
wasmsores. e : aos4s 9Qf H. D. Thornburg, Chief, Field Support and Enforcement Branch, Directorate of Regulatory Operations, Headquarters THRU: Norman C. Moseley, Director, Region II, Directorate of Regulatory Operations DUKE POWER COMPANY (CCONEE 3) DOCKET No. 50-287 - STATUS OF COMPLETION Reference my memorandu= to you dated June 14, 1974, concerning:the licensing of Oconee 3.
A final prelicensing inspection was conducted on July 9-12, 1974, to determine the status of unresolved items identified-in the referenced memorandum. All of the items labeled " Items to be Completed Prior to Licensing," are considered by Region II to be satisfactorily resolved for licensing purposes. Resolution of the items in Section A of the June 14 memotandum completes the Region II pre-licensing.inspectic7 program. Based upon the findings of our inspection program, conducted per the Regulatory Operations Manual for the construction and testing phases, Region II finds Oconee 3 ready for issuance of an operating license.
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Those items which remain outstanding as of July 17, 1974, which Region Il evaluates as requiring resolution prior.to initial criticality, are identified below. DPC has verbally committed to resolving these items and has stated that a letter of commitment will be transmitted to DL at the time a request for an operating license is made.
A copy of the letter will also be forwarded to Region II.
Items to be Resolved Prior to Initial Criticality 1.
Install and test filter elements in the gas waste disposal filter housing, penetration room and control room.
2.
Install two missing incore detector cables.
3.
Install two missing bolts on reactor building equipment hatch.
4.
Satisfactory resolution of deficiencies identified in the six listed preoperational tests:
TP 150/6 - Leak rate test of pneumatic isolation valves.
a.
b.
TP 161/3 - RB purge system functional and operational test.
TP 200/23A - Calibration of instrumentation of RCP motors.
c.
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TP 202/7 - HPI system functional and operational test.
- e..TP 600/11 - Erargency feedwater and steam generator control test.
f.
TP 600/12A - Pressurizer heater control and spray flow test.
W. C. Seidle, Chief Facilities Test and Startup Branch TRANSMITTED VIA CMC 7/17/74 3:45 p.m.
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