TXX-4807, Interim Deficiency Rept CP-86-13 Re Computer Entry Error Which Could Invalidate Portions of Jet Impingement Load Review for high-energy Piping.Initially Reported on 860305. Next Rept by 860613: Difference between revisions

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{{#Wiki_filter:Log # TXX-4807 File # 10110     .
{{#Wiki_filter:Log # TXX-4807 File # 10110 l
l k
k TEXAS UTILITIES GENERATING COMPANY SKYW AY TOWER. 400 NORTH OLIVE STREET. L.B. A L. DALLAN. TEXA8 75301 May 16, 1986
TEXAS UTILITIES GENERATING COMPANY SKYW AY TOWER . 400 NORTH OLIVE STREET. L.B. A L . DALLAN. TEXA8 75301 May 16, 1986
.OM71?Sfn'.5 Mr. Eric H. Johnson, Director Division of Reactor Safety and Projects U. S. Nuclear Regulatory Commission 611 Ryan Plaza Drive, Suite 1000 Arlington, TX 76012 l
  .OM71?Sfn'.5 Mr. Eric H. Johnson, Director Division of Reactor Safety and Projects U. S. Nuclear Regulatory Commission 611 Ryan Plaza Drive, Suite 1000 Arlington, TX 76012 l    


==SUBJECT:==
==SUBJECT:==
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==Dear Mr. Johnson:==
==Dear Mr. Johnson:==
On March 5,1986, we verbally notified your Mr. T. F. Westerman of a deficiency involving a computer entry error which could invalidate portions of the jet impingement load review for high energy piping. This is an interim report of a potentially reportable item under the provisions of 10CFR50.55(e). We have submitted an interim report logged TXX-4753, dated April 4,1986.
On March 5,1986, we verbally notified your Mr. T. F. Westerman of a deficiency involving a computer entry error which could invalidate portions of the jet impingement load review for high energy piping. This is an interim report of a potentially reportable item under the provisions of 10CFR50.55(e). We have submitted an interim report logged TXX-4753, dated April 4,1986.
Gibbs & Hill conducted a study of the adequacy of the jet load calculations.
Gibbs & Hill conducted a study of the adequacy of the jet load calculations.
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We are continuing our evaluation and anticipate submitting our next report by June 13, 1986.
We are continuing our evaluation and anticipate submitting our next report by June 13, 1986.
Very truly yours, f
Very truly yours, f
W. G. Counsil JCH/arh c - NRC Region IV (0 + 1 Copy) l Director Inspection & Enforcement (15 copies) i           U. S. Nuclear Regulatory Commission Washington, D.C.       20555 M N DO                 p                             -
W. G. Counsil JCH/arh c - NRC Region IV (0 + 1 Copy) l Director Inspection & Enforcement (15 copies) i U. S. Nuclear Regulatory Commission Washington, D.C.
20555 M N DO p
f 0
f 0
s A suvssuou or rexas vmmen usscrusc coursur l
s l
L}}
A suvssuou or rexas vmmen usscrusc coursur L}}

Latest revision as of 12:28, 10 December 2024

Interim Deficiency Rept CP-86-13 Re Computer Entry Error Which Could Invalidate Portions of Jet Impingement Load Review for high-energy Piping.Initially Reported on 860305. Next Rept by 860613
ML20198E428
Person / Time
Site: Comanche Peak 
Issue date: 05/16/1986
From: Counsil W
TEXAS UTILITIES ELECTRIC CO. (TU ELECTRIC)
To: Johnson E
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV)
References
CP-86-13, TXX-4807, NUDOCS 8605280003
Download: ML20198E428 (1)


Text

Log # TXX-4807 File # 10110 l

k TEXAS UTILITIES GENERATING COMPANY SKYW AY TOWER. 400 NORTH OLIVE STREET. L.B. A L. DALLAN. TEXA8 75301 May 16, 1986

.OM71?Sfn'.5 Mr. Eric H. Johnson, Director Division of Reactor Safety and Projects U. S. Nuclear Regulatory Commission 611 Ryan Plaza Drive, Suite 1000 Arlington, TX 76012 l

SUBJECT:

COMANCHE PEAK STEAM ELECTRIC STATION (CPSES)

DOCKET N0. 50-445 JET IMPINGEMENT LOAD REVIEW SDAR: CP-86-13 (INTERIM REPORT)

Dear Mr. Johnson:

On March 5,1986, we verbally notified your Mr. T. F. Westerman of a deficiency involving a computer entry error which could invalidate portions of the jet impingement load review for high energy piping. This is an interim report of a potentially reportable item under the provisions of 10CFR50.55(e). We have submitted an interim report logged TXX-4753, dated April 4,1986.

Gibbs & Hill conducted a study of the adequacy of the jet load calculations.

This study concluded that the jet load calculations are correct except for those components where a " shape factor" of less than 1.0 was used. Site engineering will review all component shape factors whose jet loads were calcu-lated using the PIPSCIN jet load program. After this review a schedule will be established to resolve any resulting non-conservative components.

We are continuing our evaluation and anticipate submitting our next report by June 13, 1986.

Very truly yours, f

W. G. Counsil JCH/arh c - NRC Region IV (0 + 1 Copy) l Director Inspection & Enforcement (15 copies) i U. S. Nuclear Regulatory Commission Washington, D.C.

20555 M N DO p

f 0

s l

A suvssuou or rexas vmmen usscrusc coursur L