ML20073S138
| ML20073S138 | |
| Person / Time | |
|---|---|
| Site: | South Texas  |
| Issue date: | 04/27/1983 |
| From: | Oprea G HOUSTON LIGHTING & POWER CO. |
| To: | Jay Collins NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| References | |
| 10CFR-050.55E, 10CFR-50.55E, ST-HL-AE-951, NUDOCS 8305060456 | |
| Download: ML20073S138 (4) | |
Text
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The Light Company
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, ax s 7700i <7,33 m.ni, April 27,1983 ST-HL-AE-951 File No.: G12.122 p@@ 3(]Q/[M[rN Mr. John T. Collins
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Regional Administrator, Region IV Nuclear Regulatory Commission
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611 Ryan Plaza Dr., Suite 1000 g
Arlington, Texas 76012
Dear Mr. Collins:
South Texas Project Units 1 & 2 Docket Nos. STN 50-498, STN 50-499 1b-}7 Final Report Concerning Motor Operator Weights for Valves On June 29, 1982, pursuant to 10CFR50.55(e), Houston Lighting & Power Company (HL&P) notified your office of an item concerning incorrect weights for motor operators used in stress analyses performed on valves supplied by the Anchor Darling Valve Company. Attached is the final report concerning this item.
If you should have any questions concerning this item, please contact Mr. Michael E. Powell at (713) 877-3281.
Very truly yours, A
l G. W. Oprea, Jr.
Executive Vice President MEP/kr Attachment 8305060456 830427 PDR ADOCK 05000498 S
April 27, 1983 Ifouston Lighting & Power Company ST-HL-AE-951 cc:
G. W. Oprea, Jr.
File Number: G12.122 J. H. Goldberg Page 2 J. G. Dewease J. D. Parsons D. G. Barker M. R. Wisenburg R. A. Frazar J. W. Williams R. J. Maroni J. E. Geiger H. A. Walker S. M. Dew J. T. Collins (NRC)
H. E. Schierling (NRC)
W. M. Hill, Jr.
(NRC)
M. D. Schwarz (Baker & Botts)
R. Gordon Gooch (Baker & Botts)
J. R. Newman (Lowenstein, Newman, Reis, & Axelrad)
STP RMS Director, Office of Inspection & Enforcement Nuclear Regulatory Commission Washington, D. C.
20555 G. W. Muench/R. L. Range Charles Bechhoefer, Esquire Central Power & Light Company Chairman, Atomic Safety & Licensing Board P. O. Box 2121 U. S. Nuclear Regulatory Commission Corpus Christi, Texas 78403 Washington, D. C.
20555 H. L. Peterson/G. Pokorny Dr. James C. Lamb, III City of Austin 313 Woodhaven Road P. O. Box 1088 Chapel Hill, North Carolina 27514 Austin, Texas 78767 J. B. Poston/A. vonRosenberg Mr. Ernest E. Hill City Public Service Board Lawrence Livermore Laboratory P. O. Box 1771 University of California San Antonio, Texas 78296 P. O. Box 808, L-46 l
Livermore, California 94550 Brian E. Berwick, Esquire William S. Jordan, III Assistant Attorney General Harmon & Weiss for the State of Texas 1725 I Street, N. W.
P. O. Box 12548 Suite 506 Capitol Station Washington, D. C.
20006 Austin, Texas 78711 Lanny Sinkin Citizens for Equitable Utilities, Inc.
Citizens Concerned About Nuclear Power c/o Ms. Peggy Buchorn 5106 Casa Oro Route 1, Box 1684 San Antonio, Texas 78233 Brazoria, Texas 77422 Jay Gutierrez, Esquire Hearing Attorney Office of the Executive Legal Director U. S. Nuclear Regulatory Commission Washington, D. C.
20555 Revision Date 12-20-82
Final Report Concerning Motor Operator Weights for Valves I.
Summary Thirteen (13) Anchor Darling motor operated valves were identified as having actual weights greater that those specified on the drawings as required by specification 1L5291S0100.
It was determined that only three (3) stress packages should be re-analyzed since the stress margin available in those packages was potentially insufficient to compensate for the increase of the valve weights. The valves involved are located in the Component Cooling Water System (valve # CC-392), Main Steam Line (valve # MS-143), and Liquid Waste Processing System (valve # WL-312).
These valves perform system isolation and/or containment isolation 7
safety functions. The resolution of this problem is given in Section III of this report.
II. Description of Deficiency Refer to the first interim report transmitted to the NRC on July 28, 1982 (ST-HL-AE-857).
III. Corrective Action Actual weights of the valves were obtained and stress analysis performed for two of the three valves: CC-392 and WL-312.
No physical modifications to the piping system, supports, or valves were found to be l
necessary. The third valve, MS-143 is located in the Main Steam t
Isolation Valve Cubicle (MSIVC). A major change in the piping layout in the MSIVC is being made as reported to the NRC October 27, 1982 (ST-HL-AE-896). As a part of this redesign, the stress analysis for MS-143, using the actual weight, will be redone in accordance with the Engineering Intermediate Schedule.
In addition, Bechtel has confirmed with the vendor the actual weights of the two (2) valves referenced in our first interim report which are located in the Fire Protection System and Radioactive Vents and Drain l
System (ED-064 and FP-756). Bechtel has determined that the actual weights are within the stress margin available for their respective applications.
No further corrective action is required for these valves.
(
IV. Recurrence Control l
A recurrence control program is not required because the events were I
unique. Further, Bechtel procedures, practices, and policies are now in effect which require confirmation frcm primary vendors of data utilized in final design calculations.
V.
Safety Analysis Reanalysis for valves CC-392 and WL-312 using the actual weights showed that the valves are acceptable and an overstress condition in the piping system does not exist. A detailed reanalysis and safety evaluation for valve MS-143 was not performed because reanalysis will be done in conjunction with the MSIVC redesign, e
r l
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