ML19284A834

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Final Deficiency Rept Re Erroneous Steam Generator Level Indications During High Energy Line Breaks Inside Containment.Westinghouse Developing Temp Compensation Mod to Ref Leg Sensor
ML19284A834
Person / Time
Site: Marble Hill
Issue date: 02/06/1980
From: Shields S
PSI ENERGY, INC. A/K/A PUBLIC SERVICE CO. OF INDIANA
To:
References
NUDOCS 8002200579
Download: ML19284A834 (1)


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q y PUBLIC SERVICE February 6, 1980 INDIANA Docket Nos.:

STN 50-5!.6 S. W. Shields Sri 50-547 Vice Presdent E'ectric System Cons truction Permit Nos. :

CP!R-170 CPPR-171 Mr. Ja=es G. Keppler, Director U.S. Nuclear Regulatory Cc= mission Region III 799 Roosevelt Road Glen Ellyn, IL 60137 Marble Hill Nuclear Generating S tation Units 1&2

Dear Mr. Keppler:

~

On January 16, 1980, Mr. C.E. Chmielewski of Public Service Company of Indiana, Inc. (PSI) telephoned your office to notify you of a potentially reportable incident as required by 10CFR50.55(e).

Ihe following report resolves that ites and constitutes a final report under the Regulation.

In their June 22, 1979 letter (NS-DiA-2104) to your Mr. S tello, Wes tinghouse identified the potential for errenous steam generator level indications during high energy line breaks inside contain=ent.

This letter discussed the possible consequences of such an occurrence and contained interim solutions for plants currently in operation.

Interim solutions for operating plants involve either changing the icw-low steam generator water level set points or insulating the steam generator reference leg.

As a long term solution, for plants such as Marble Hill, Westinghouse is developing a te=perature compensation modification to the reference leg sensor.

PSI will conitor the development of this temperature compensation modification and if appropriate, implement this change on Marble Hill.

Should it occ-r that Westinghouse does not develop this modification, PSI will incorporate the interim changes involving either changing the low-low steam generator water level set points or insulating the steam generator reference les prior to fuel load.

If you have any questions, please feel free to contact =e.

Sincerely, IDG:jj 3o/7 cc:

Director of Inspection & Enforcement S.W. Shields N-U.S. Nuclear Regulatory Co ission g

Washington, D.C.

20555 E.R. Schweibinz, P.E.

g 022oo J.J. Harrison 1000 East Main Street. ?!ainfield, indiana 16168 317 839.9611