ML19209C888

Forwards Final Deficiency Rept Re Invalid Heat Treatment of Reactor Pressure Vessel Pedestal Studs

ML19209C888
Person / Time
Site:	Hartsville, Phipps Bend
Issue date:	10/11/1979
From:	Mills L TENNESSEE VALLEY AUTHORITY
To:	James O'Reilly NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
Shared Package
ML19209C889	List: ML19209C888 ML19209C899
References
NUDOCS 7910180443
Download: ML19209C888 (1)

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TENNESSEE VALLEY AUTHORITY CH ATTANOOGA. TENNESSEE 374o1 400 Chestnut Street Tower II October 11, 1979

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Mr. James P. O'Reilly, Director Office of Inspection and Enforcement U.S. Nuclear Regulatory Commission Region II - Suite 3100 101 Marietta Street Atlanta, Georgia 30303

Dear Mr. O'Reilly:

HARTSVILLE AND PHIPPS BEND NUCLEAR PLANT ALL UNITS - REPORTABLE DEFICIENCY - INVALID HEAT TREAINENT OF REACTOR PRESSURE VESSEL PEDESTAL STUDS (NCR S-10)

Initial report of the subject deficiency was made to W. B. Swan, NRC-CIE, Region II, on September 12, 1979. In compliance with paragraph 50.55(e) of 10 CFR Part 50, we are enclosing the final report of the subject deficiency. If you have any questions regarding this matter, please call Tish Jenkins at FTS 854-2014.

Very truly yours, TENNFSSEE /ALLET AUTHORITT L. M. Mills, Manager Nuclear Regulation and Safety Enclosure cca Mr. Victor Stallo, Director (Enclosure)

Office of Inspection and Enforcement U.S. Nuclear Regulatory Commission Washington, DC 20555

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1176 168 l

7 910] 80 f d/3 h '5

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