ML20076F440
| ML20076F440 | |
| Person / Time | |
|---|---|
| Site: | Marble Hill |
| Issue date: | 08/17/1983 |
| From: | Shield S, 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-0114-83, SVP-114-83, NUDOCS 8308260035 | |
| Download: ML20076F440 (2) | |
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PUBLIC SERVICE INDIANA S. W. Shields senior vice President.
August 17, 1983 Nuclear Division S83-32 SVP-Oll4-83 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 August 2,1983, Mr. P. R. Pelke of your office requested additional information in the matter of a 10 CFR 50.55(e) potentially reportable item. Public Service Company of Indiana, Inc. (PSI) hereby submits a more detailed letter which supersedes the letter dated July 29, 1983 (SVP-Olll-83).
On July 1, 1983, Mr. L. G. Yeager of PSI notified your office of a potentially reportable item as required by 10 CFR 50.55(e). A PSI audit of Sargent & Lundy (S&L), PSI's architect engineer, identified 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 temper-ature 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
..f 17,650 psi at 210 F in the Marble Hill 1CS01 Revision 3 dated May 28, 1981 and ICS02 Revision 1 dated May 28, 1981 piping stress calculations. These calculations 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, p
1983 8308260035 830817
$G19 PDR ADOCK 05000546 S
PDR P. O. Box 190, New Washington, Indiana 47162 812. 289.3000 j
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PUBUC SERVICE INDIANA Letter:
J. G. Keppler August 17, 1983 S83-32 SVP-0114-83 Sargent & Lundy is currently reviewing stress reports for design inconsistencies to determine the scope of the problem. Any incon-sistencies identified will be addressed in the stress report addenda or revisions. 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 November 18, 1983.
If you have any questions regarding this matter, please contact me at your convenience.
Sincerely,
,f S. W. Shields SWS/LCY/bak cc: Director of Inspection and Enforcement U. S. Nuclear Regulatory Commission Washington, D. C.
20555 J. E. Konklin J. F. Schapker l
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