TXX-6282, Final Deficiency Rept CP-86-66 Re Noncontact Lap Splices in Auxiliary Bldg.Initially Reported on 860926.Engineering Calculations & Review of Applicable Quality Documents Completed.Issue Not Reportable Per 10CFR50.55(e)
| ML20211H330 | |
| Person / Time | |
|---|---|
| Site: | Comanche Peak  |
| Issue date: | 02/18/1987 |
| From: | Counsil W, Keeley G TEXAS UTILITIES ELECTRIC CO. (TU ELECTRIC) |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| CP-86-66, TXX-6282, NUDOCS 8702260149 | |
| Download: ML20211H330 (2) | |
Text
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l Log # TXX-6282
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File # 10110 P9 903.8
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Ref. : 10CFR50.55(e) 3 lilELECTRIC February 18, 1987 m,,,, c, %,
Emuine lhe Arskinst U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D. C. 20555
SUBJECT:
COMANCHE PEAK STEAM ELECTRIC STATION (CPSES)
DOCKET NOS. 50-445 AND 50-446 NON-CONTACT LAP SPLICES IN THE AUXILIARY BUILDING SDAR:
CP-86-66 (FINAL REPORT)
Gentlemen:
On September 26, 1986, we verbally notified your Mr. I. Barnes of a potential deficiency regarding vertical rebar in the Auxiliary Building that apparently does not satisfy the criteria of an ACI code defined lap splice.
Specifically, the issue involves rebar identified during an investigation conducted in accordance with the Comanche Puk Response Team (CPRT) Issue Specific Action Plan (ISAP) II.a for missing reinforcing steel. Our last interim report logged was TXX-6136 dated December 5, 1986.
Previous reports indicated the issue involved t e vertical dowels and two lap splice bars which had not been installed with, prescribed design locations.
One of the lap splices did not conform to ACI Code requirements for non-contact lap splices. Consistent with our plan of evaluation, engineering calculations and the review of applicable quality documents have been completed.
In our analysis, the inactive reinforcing bars were discounted from the strength calculation. The remaining area of reinforcement bars available was found to be greater than the area required in the original design. The design input obtained from the original design is subject to confirmation in accordance with our ongoing Corrective Action Program.
This analysis, documented per calculation number 16345/6-CS(S)-076, Rev. O, has established the acceptability of the original deviation. The deviation has no adverse affects on the safety of plant operations or structural integrity of the Auxiliary Building. Therefore in the event this issue had remained undetected, no condition adverse to safety would exist.
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400 North Olise Street L H. 81 Dallas,lexas 75201
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TXX-6282 February 18, 1987 Page 2 Based upon these results, we have concluded this issue is not reportable under the provisions of 10CFR50.55(e). Records supporting this documentation are available for your inspectors review at the CPSES site.
Very truly yours, W. G. Counsil By: X.
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G. S. Keeley Manager,NuclearL%nsing-JCH/mlh c - Mr. E. H. Johnson, Region IV Mr. D. L. Kelley, RI - Region IV Mr. H. S. Phillips, RI - Region IV 4
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