ML17244A735

Responds to IE Bulletin 79-13, Cracking in Feedwater Sys Piping, Item 5.Feedwater Nozzle Inspected & Evaluated. Emergency Procedures Adequately Cover Feedwater Line Break Accident

ML17244A735
Person / Time
Site:	Ginna
Issue date:	07/12/1979
From:	White L ROCHESTER GAS & ELECTRIC CORP.
To:	Grier B NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
References
NUDOCS 7908070452
Download: ML17244A735 (4)

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As ~ 10 1 ~ 40 10AA IIA'IC ROCHESTER GAS AND ELECTRIC CORPORATION ~ 89 EAST AVENUE, ROCHESTER, N.Y. 14649 LEON D. WHITE. JR. TCL.EPHON6 VICE I'RE9IOENT ARK* COOE 716 546-2700 July 12, 1979 Mr. Boyce H. Grier, Director U. S. Nuclear Regulatory Commission Office of Inspection and Enforcement Region I 631 Park Avenue King of Prussia, Pennsylvania 19406

Subject:

IE Bulletin 79-13, Cracking in Peedwater System Piping, item 5 R. E. Ginna Nuclear Power Plant, Unit 41 Docket No. 50-244

Dear Mr. Grier:

In response to Inspection and Enforcement Bulletin 79-13 item 5 con-cerning schedule for feedwater pipe to steam generator nozzle inspection, procedures for response to a feedwater line break accident, and detection of feedwater leaks, the following information is provided.

a. The feedwater nozzle inspection and evaluation has been com-pleted and the expanded program as directed in the bulletin is presently in progress.

b. A review of plant emergency procedures has been completed.

Emergency procedures are in effect for loss of feedwater which adequately'over a feedwater line break accident upstream of the feedwater check valve. A feedwater line break accident downstream of the feedwater check valve would produce indica-tions and responses similar to a steam line break accident, which is also adequately covered.

c. Detection of leakage in containment includes several systems

'hich are in addition to measures based on radioactivity or reactor coolant inventory and would indicate feedwater leaks.

One of these, the condensate measuring system, collects moisture condensed from the containment'tmosphere by the containment fan cooler units. This system provides a depend-able and accurate means of determining leakage, with the ability to detect leakage as low as 0.5 gpm. The containment humidity detector system provides backup to this system with yoP80V 0

0 ROCHESTER GAS AND ELECTRIC P. sHEET No. 2 DATE July 12, 1979 Mr. Boyce H. Grier, Director the ability to detect approximately 2 gpm leakage. Contain-ment sump pump actuations are also observed to determine increased leakage. These methods and sensitivities are des-cribed in the bases of the Ginna Plant Technical Specifications.

Very truly yours,

~

y L.. D. White, Jr.

xc: U. S. Nuclear Regulatory Commission Office of Inspection and Enforcement Division of Reactor Operations Inspection Washington, D. C. 20555

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