TXX-6028, Final Deficiency Rept CP-86-57 Re Reinforcing Steel in Facility Reactor Cavity Wall.Initially Reported on 860829. Design Restored to Condition Specified in Revised Drawing. Item Not Reportable Per 10CFR50.55(e)

Final Deficiency Rept CP-86-57 Re Reinforcing Steel in Facility Reactor Cavity Wall.Initially Reported on 860829. Design Restored to Condition Specified in Revised Drawing. Item Not Reportable Per 10CFR50.55(e)

ML20215H282
Person / Time
Site:	Comanche Peak
Issue date:	10/15/1986
From:	Counsil W TEXAS UTILITIES ELECTRIC CO. (TU ELECTRIC)
To:	Johnson E NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV)
References
CP-86-57, TXX-6028, NUDOCS 8610230068
Download: ML20215H282 (2)

Text

-

~ Log # TXX-6028 File # 10110 903.8 TEXAS UTILITIES GENERATING COMPANY SKYWAY TOWER . 400 NORTH OLIVE STREET,1.B. 88 . DALLAS. TEXAS 75308 October 15, 1986

.* Met???aa pkg@g[W/@%

i' OCTI51986 ]

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

L- (' ,

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 REINFORCING STEEL IN UNIT 1 REACTOR CAVITY WALL SDAR: CP-86-57 (FINAL REPORT)

Dear Mr. Johnson:

On August 29, 1986, we verbally notified your Mr. T. F. Westerman of a deficiency involving the reinforcing steel in the Unit I reactor cavity wall.

Specifically, additional reinforcing steel for the wall was specified and deleted through subsequent drawing revisions without supporting design calculations. We have submitted an interim report logged TXX-5050, dated September 29, 1986.

The concrete placement of the reactor cavity wall between elevations 812'-0" and 819'-0 1/2" was constructed in accordance with Revision 2 of drawing 2323-S1-0572. Subsequently, Revision 3 of the drawing required additional reinforcing steel . The additional reinforcing steel was specified (based upon engineering judgement) to minimize the possibility of cracking.

Specific calculations justifying the adequacy of the wall, without the additional reinforcing steel shown in Revision 3, were not generated because the design was restored to conditions specified per Revision 2 of the drawing.

Subsequently, additional calculations- have been generated which demonstrate that the omission of the additional reinforcing does not impair the structural integrity of the reactor cavity wall, and the as-built reinforcement configuration is adequate.

%o2gy M g S

s unvmos or rrxss enursrs rt rcrure amruv

,p

TXX-6028 October 15, 1986 Page 2

' ~

We have concluded that in the event the condition had remained undetected, no condition adverse to safety would exist. The issue is not repor. table under the provisions of 10CFR50.55(e). Records supporting these conclusions are available for your inspectors to review at the CPSES project site.

Very truly yours, W. G. Counsil JCH/amb c - NRC Region IV (0 + 1 copy)

Director, Inspection & Enforcement (15 copies)

U. S. Nuclear Regulatory Commission Washington, D.C. 20555 l

i I

(

i

- - . _ - . . . . _ . . . - . , . . . . , _ . . . . . . _ . , , . . _ _ . . . - _ , . _ _ . _ . . . _ . _ . , _ , . . . . . . . . . . . - . . - _ . . _ _ . . . . . , . . . ~ _ _ .