ML19312C822

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Provides Status of Const Completion & Identifies Items to Be Resolved Prior to Initial Criticality.Facility Ready for OL
ML19312C822
Person / Time
Site: Oconee Duke Energy icon.png
Issue date: 07/17/1974
From: Seidle W
US ATOMIC ENERGY COMMISSION (AEC)
To: Thornburg H
US ATOMIC ENERGY COMMISSION (AEC)
Shared Package
ML19312C818 List:
References
NUDOCS 8001100732
Download: ML19312C822 (2)


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H. D. Thornburg, Chief, Field Support and' Enforcement Branch, Directorate of Regulatory Operations, Headquarters THRU: l'orman C. Moseley, Director, Region II, Directorate of Regulatory Operations DUKE POWER COMPAIPI (OCONEE 3) DOCKET No. 50-287 - STATUS OF COMPLETION Reference my memorandum 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 memorandum completes the Region II pre-licensing inspection program.

Based upon the findings of our inspection program, conducted per the Regulatory Operations Manual for the construction and testing phases, Region II finds Oconec 3 ready for issuance of an operating license. _

Those items which remain outstanding as of July 17, 1974, which Region II 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 contr'o1 room.

I 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.

TP 600/11 - Emergency feedwater and steam generator control test, d.

TP 600/12A - Pressurize.r heater control and spray flow test.

e.

f.

W. C. Seidle, Chief Facilities Test and Startup Branch TPJJISMITTED VIA CMC 7/17/74 3:45 p.m.

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