ML19316A071

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Forwards Inquiry Rept 50-269/72-08 Re 720828 Break of Pneumatic Hose within Primary Inlet Chamber of Once Through Steam Generator a
ML19316A071
Person / Time
Site: Oconee Duke Energy icon.png
Issue date: 09/05/1972
From: Murphy C
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
To: Henderson J
US ATOMIC ENERGY COMMISSION (AEC)
Shared Package
ML19316A072 List:
References
NUDOCS 7911210743
Download: ML19316A071 (1)


See also: IR 05000269/1972008

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UNITED STATES

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ATOMIC ENERGY COMMISSION

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DIRECTORATE OF REGULATORY OPERATIONS

September 5, 1972

J. B. Henderson, Chief, Reactor Construction Branch (2)

Directorate of Regulatory Operations, Headquarters

RO INQUIRY REFORT NO. 50-269/72-8

DUKE POWER COMPANY (OCONEE 1), LICENSE NO. CPPR-33, DOCKET NO. 50-269,

DAMAGE TO TUBE ENDS IN PRIMARY INLET CHAMBER OF STEAM GENERATOR A

The attached Inquiry Report is forwarded for information.

Duke has stated that the repairs vill not affect the plant schedule

and that they do not censider the incident to be reportable under

the requirements of 10 CFR 50 55(e). Based upcn the information

presented, we concur in this position. The assigned inspector viu

review this incident during the next inspection.

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C. E. Mirph' , Ac.ing Chief

RO:II:CEM

Reactor Test and Startup Branch

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Enclosure:

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RO Inquiry Ept. No.

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50-269/72-8 (Jape)

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J. G. Keppler, RO

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RS, AD For Safety and Security Stds. (3)

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L Asst. Director For Boil. Water Reactors (2)

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L Asst. Director For Press. Water Reactors (2)

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L Asst. Director For Operating Reactors (3)

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L Asst. Directer For Site Safety (2)

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RO Office of Operations Evaluation

R0 Asst. Dir. for Procedures

R0 Asst. Dir. for Inspection & Enforcenent

RO Files

DR Central Files

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RO Inquiry Ept. No.

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50-269/72-8

Hampton stated that the procedure for repairing the damage vill

be the veld repair procedures currently in use for OTSG A.

2.

Hampton stated that the da= age vill require approxi=ately one veek

to repair and the Unit 1 fuel loading schedule will not be affected

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