TXX-6063, Interim Deficiency Rept CP-85-26 Re Steam Generator Upper Lateral Restaint Embedment Design.Initially Reported on 850719.Analysis of Issue Based on Revised Loadings on Beams & Beam Connections.Next Rept Expected by 861203

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Interim Deficiency Rept CP-85-26 Re Steam Generator Upper Lateral Restaint Embedment Design.Initially Reported on 850719.Analysis of Issue Based on Revised Loadings on Beams & Beam Connections.Next Rept Expected by 861203
ML20211H414
Person / Time
Site: Comanche Peak 
Issue date: 10/27/1986
From: Counsil W
TEXAS UTILITIES ELECTRIC CO. (TU ELECTRIC)
To: Johnson E
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV)
References
CP-85-26, TXX-6063, NUDOCS 8611050127
Download: ML20211H414 (1)


Text

r Log # TXX-6063 File # 10110 903.8-TEXAS UTILITIES GENERATING COMPANY SKYWAY TOWER = est NORTH OLIVE ErrREET. I.B. 88. DAI.I AS TEXAS 7539I October 27, 1986 "Y1".ih.US, j [ [h y!

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OCT 311986

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Mr. Eric H. Johnson, Director-Division of Reactor Safety and Projects

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U. S. Nuclear Regulatory Commission 611 Ryan Plaza Drive, Suite 1000 Arlington, TX 76012

SUBJECT:

COMANCHE PEAK STEAM ELECTRIC STATION (CPSES)

DOCKET N0. 50-445 UPPER LATERAL RESTRAINT EMBEDMENT DESIGN SDAR: CP-85-26 (INTERIM REPORT)

Dear Mr. Johnson:

On July 19, 1985, we verbally notified your Mr. D. Powell of a deficiency regarding the Unit 1 steam generator upper lateral restraint embedment design.

This is an interim report of a potentially reportable item under the provisions of 10CFR50.55(e). Our last interim report was' logged.TXX-4961 dated August 18, 1986.

The scope of this issue has been expanded in order to analyze the steam generator upper lateral restraint embedments based on revised loadings on the beams and their connections. These revised loadings are a result of a design.

bounding assumption that the Steam Generator compartment platforms are considered removed.

Prior designs were based upon attenuation of pressure loadings in the upper compartment regions due to the restricting effects of compartment platforms located in the vent paths.

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We anticipate submitting our next report on this issue no later than December 3, 1986.

Very truly yours, V/20 W.' G. Counsil BSD/amb c - NRC Region IV (0 4 1 copy)

Director, Inspection & Enforcement (15 copies)

U. S. Nuclear Regulatory Commission Washington, D.C.

20555 8611050127 861027 PDR ADOCK 05000445.

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