ML20082J794

Interim Deficiency Rept Re Use of Incorrect Input Values in Design Calculations.Sargent & Lundy Requested to Perform Addl Work Re Incorrect Thermal & Seismic Header Displacements Used in Subsystem 1CS06

ML20082J794
Person / Time
Site:	Marble Hill
Issue date:	11/18/1983
From:	Shields S PSI ENERGY, INC. A/K/A PUBLIC SERVICE CO. OF INDIANA
To:	James Keppler NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
References
10CFR-050.55E, 10CFR-50.55E, S83-32, SVP-0159-83, SVP-159-83, NUDOCS 8312020314
Download: ML20082J794 (2)

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PUBLIC SERVICE INDIANA S. W. Shields senior vice President - November 18, 1983 Nuclear Division S83-32 SVP-0159-83 Mr. James G. Keppler, Docket Nos.: STN 50-546 Regional Administrator STN 50-547 U. S. Nuclear Regulatory Commission Construction Permit Nos.:

Region III CPPR - 170 799 Roosevelt Road CPPR - 171 Glen Ellyn, Illinois 60137 Marble Hill Nuclear Generating Station - Units 1 and 2

Dear Mr. Keppler:

On July 1,1983, Mr. L. G. Yeager of Public Service Company of Indiana, Inc. (PSI) notified your office of a potentially reportable item as I required by 10 CFR 50.55(e) . A PSI audit of Sargent & Lundy (S&L),

PSI's architect engineer, identified two findings involving the use of incorrect input values in design calculations. The Marble Hill piping design specification for the Containment Spray System gave a system temperature of 300 F. However, the Marble Hill FSAR indicated a system temperature of 260 F. It was later determined that the temperature of 260 F was correct. The A.S.M.E. Boiler and Pressure Vessel Code Section III, Appendix I,1974 Edition through the Summer 1976 Addenda states that the allowable stress for SA-312 TP-304 material at 260 F is 17,080 psi. Contrary to this, S&L used an allowable stress of 17,650 psi at 2100F in the Marble Hill 1CS01 Revision 3 dated May 28, 1981 and ICS02 Revision 1 dated May 28, 1981 piping stress , calculations. These calcu-lations are for specific analytical subsystems of the Unit 1 Containment Spray System. The resultant decrease in allowable stress to 17,080 psi in the calculations means that prior to the audit finding, the original value of 17,650 psi used by S&L could have potentially allowed stresses in excess of A.S.M.E. Code requirements. These types of situations could potentially allow a situation to arise whereby the safe operations of the plant could be adversely affected. The second finding involved multiple problems dealing primarily with incorrect thermal and seismic header displacements used in the analysis of subsystem 1CS06.

O o PDR MOV O P. O. Box 190, New Washington, Indiana 47162 812. 289 .3000 EU kQ

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pusuc SERVICE INDIANA Letter: J. G. Keppler November 18, 1983 S83-32 SVP-0159-83 Sargent & Lundy has reviewed 68 additional stress reports for design inconsistencies to determine the scope of the problem. PSI has requested Sargent & Lundy to do additional work pertaining to the second finding.

PSI submittal of a final report will await satisfactory disposition and closeout of both findings. If any impact on issued piping or supports is determined to exist, appropriate corrective action will be taken.

This letter is intended to fulfill the requirements of an interim report as required by 10 CFR 50.55(e). A further report will be filed on or before February 10, 1984. If you have any questions regarding this matter, please contact me at your convenience.

Sincerelyr ?

. &&:s S. W. Shields SWS/LGY/bak cc: Director of Inspection and Enforcement U. S. Nuclear Regulatory Commission Washington, D. C. 20555 J. E. Konklin

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