ML18139A697
| ML18139A697 | |
| Person / Time | |
|---|---|
| Site: | Surry, North Anna  |
| Issue date: | 08/08/1980 |
| From: | Sylvia B VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.) |
| To: | James O'Reilly NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| References | |
| 695, IEB-79-03A, IEB-79-3A, NUDOCS 8009020242 | |
| Download: ML18139A697 (2) | |
Text
VIRGINIA ELECTRIC AND PowE~ :.~~~:)>ANY.'.. : :
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RICHXOND,VIlil!Gllir.IA 23261. *; *, ' **'..-.
August 8, 1980
-:O t.UG 11 All: 05 Mr. James P. O'Reilly, Director Office of Inspection and Enforcement U.S. Nuclear Regulatory Commission Region II 101 Marietta Street, Suite 3100 Atlanta, Georgia 30303
Dear Mr. O'Reilly:
I.E. BULLETIN 79-03A SURRY POWER STATION UNITS 1 AND 2 NORTH ANNA POWER STATION UNITS 1 AND 2 Serial No. 695 NO/RCC:ms Docket Nos. 50-280 50-281 50-338 50-339 License Nos. DPR-32 DPR-37 NPF-4 NPF-7 This is* in response to I.E. Bulletin 79-03A, "Longitudinal Weld Defects in ASME SA-312, Type 304 Stainless Steei Pipe,"
transmitted by NRC letter of April 4, 1980.
This letter supplements our response to I.E.Bulletin 79-03 (Serial Nos. 442 & 344B).
Vepco, as assisted by the Architect-Engineer, Stone and Webster Engineering Corporation, and the Nuclear Steam Supply System Vendor, Westinghouse Electric Corporation, has completed its review for compliance with the requirements of IE Bulletin 79-03A.
The results of that review are as follows:
Surry Power Station Units 1 and 2 Eight fittings manufactured by Flowline Corporation of
- New Castle, PA were determined as being of welded seani
- construction and subjected to system design pressures in excess of the calculated 85 percent of code allowable stresses.
Available records for four fittings do not afford the determination of the ASTM specification.
Therefore, these fittings are assumed to be constructed of SA-312/A-312 material for the purpose of this review.
The subject fittings are identified on Attachment 1.
Further review of the 300 feet of 10" SCH 40S pipe used in the Low Head Safety Injection System which was.reported in our response to IE Bulletin 79-03 determined that it is not subjected to system d~sign pressures in
- excess of
- the* calculated 85 percent of the code allowable stresses.
V
VIRGINIA ELECTRIC AND POWER COMPANY TO Mr. James P. O'Reilly 2
North Anna Power Station Units 1 and 2 Our review has determined that no SA-312 dr A-312 type 300 series fusion welded pipe in use in safety-related systems or equipment is subject to design stresses greater than 85 percent of the code ali"owable stress at the system design temperature.
Our review included the 10" SCH 408-90° elbow, located in the Recirculation Spray System which was previously reported in response to IE Bulletin 79-03.
This report completes the information required by I.E. Bulletin 79-03A.
If you require additional information or have any questions please contact us.
Attachment Very truly yours,
&_f #,_
B.R.~
Manager - Nuclear Operations and Maintenance cc:
Director -
NRC Office of Inspection and Enforcement Division of Reactor Construction Inspection Washington, D. C.
20555