ML17250A649
| ML17250A649 | |
| Person / Time | |
|---|---|
| Site: | Ginna  |
| Issue date: | 09/05/1980 |
| From: | White L ROCHESTER GAS & ELECTRIC CORP. |
| To: | Grier B NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| References | |
| IEB-79-13, NUDOCS 8010010666 | |
| Download: ML17250A649 (4) | |
Text
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89 E4ST AVENUE, ROCHESTER, N.Y. l4649 LEON D. WHITE. JR.
VICE I'REEIOENT TEI.EessOIsE AREA COOE Old 546 2700 September 5, 1980 Mr. Boyce H. Grier, Director U. S. Nuclear Regulatory Commission Office of Inspection and Enforcement Region I 631 Park Avenue King of Prussia, Pennsylvania 19406
Subject:
IE Bulletin 79-13, Revision 2, "Cracking in Feedwater System Piping" R. E. Ginna Nuclea Power Plant, Unit 41 Docket N
. 50-244
Dear Mr. Grier:
In accordance with Inspection and Enforcement Bulletin 79-13, Revision 2, dated October 17, 1979, item 2, information required as a result of an inspection program during the 1980 refueling outage of the Ginna unit is provided below.
1.
The following items received volumetric examinations:
a.
Loops A & B feedwater nozzle to elbow welds utilizing radiographic and ultrasonic, techniques with no recordable indications.
b.
Loops A & B feedwater piping welds to the first support utilizing the radiographic techniques on each loop with no recordable indications.
c.
Loops A & B feedwater pipes to containment penetration welds utilizing the radiographic techniques with no recordable indications.
d.
Fourteen inches of feedwater pipe downstream of the Standby Auxiliary Feedwater System tie in on Loops A &
B Feedwater inside Containment utilizing the radiographic techniques with no recordable indications.
80IIIeoi o(,
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OCHESTER GAS AND ELECT~CORP.
DATE September 5, 19%5 To Mr. Boyce H. Grfer, Director SHEET NO.
2 e.
Fourteen inches of Feedwater pipe downstream of the Motor Driven and Turbine Driven Auxiliary Feedwater ties on Loop A 6 B feedwater pipes outside of contain-ment utilizing the radiographic technique.
On the B-Loop feedwater there were no recordable indications; however, the A-Loop feedwater pipe revealed surface indications, examined further by the magnetic particle method and determined to be code acceptable inclusions formed during original manufacturing of the pipe.
2.
Visual examination of all feedwater pipe supports and snubbers inside containment on Loop A 6 B Feedwater with no recordable indications.
Very truly yours, L. D. White, Jr.
xc:
U. S. Nuclear Regulatory Commission Office of Inspection and Enforcement Division of Reactor Operations Inspection Washington, D. C.
20555
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