IR 05000281/1979072
| ML18136A327 | |
| Person / Time | |
|---|---|
| Site: | Surry  |
| Issue date: | 11/07/1979 |
| From: | Danielson D, Erb C, Herdt A NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML18136A326 | List: |
| References | |
| 50-281-79-72, NUDOCS 7912310115 | |
| Download: ML18136A327 (4) | |
Text
- .,
U.S. NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT
REGION II
Report No. 50-281/79-72 Docket N License No. DPR-37 Licensee:
Virginia Electric & Power Company P. 0. Box 26666 Richmond, VA 23261 Facility Name:
Surry Power Station, Unit 2 Inspection At:
Surry site near Williamsburg, Virginia Inspection Conducted:
August 27-30, 1979
~/J\\1, ~J\\_/
Inspector:
Carl M. Erb
/JJ<r/1,~ ~*~-L~lfh-v--
Approved by:
D. H. Danielson, Chief Engineering Support Section 2, RIII c;7kd;~hr~-**.. /
.ft'" Engineering Support Section 1, RII Inspection Summary Inspection on August 27-30, 1979 (Report No. 50-281/79-72)
r1 1) 1 t.1)11 Areas Inspected: Quality control records for main steam elbows and modified feed water nozzles; welding and radiography of main steam piping; radiography of feed water, and shell weld for a generator. The inspection involved a total of 24 inspector hours on site by one NRC RIII inspecto Results:
No items of noncompliance or deviations were identified.
?912310
\\ I 5
r DETAILS Persons Contacted Licensee Personnel (VEPCO)
- W. L. Stewart, Station Manager
- T. A. Peebles, Superintendent Technical Services
- C. W. Embler, Welding Superintendent - Generator Repair
- W. Skelley, Staff Assistant - Generator Repair
- J. Goodson, QualityControl Manager - Generator Repair
- M. Tower, Quality Assurance
- O. J. Costello, Administrative Assistant C. W. Rhodes, Resident Engineer R. F. Driscoll, QC Engineer Chicago Bridge and Iron Company (CBI)
J. Edgar, QA Superintendent Daniel Construction Company (DCC)
T. Lawson, QC Manager R. Davis, QC Supervisor R. Yuhasz, QC inspector Technical Services Laboratory (TSL)
D. Councill, NDE inspector, Level II
- Denotes those present at the exit intervie Functional or Program Areas Inspected Record Review The receiving records from Grinnell {P.O. 11649) for three welded main steam elbows, (32" x 30
, long radius 90°,) were examined. These fittings were source inspected by VEPCO. The material was SA515, Grade 70 and the fittings were rolled from plate with a single longitudinal wel Certifications to specification NUS 9049 for the following were on file: dimensions, base metal, weld rod, NDE, mechanical properties, magnetic particle test, and radiographic qualit :
A Certificate of Compliance, POM-19 from Westinghouse, Tampa (P.O. 21228), was on file covering the feedwater nozzles. These nozzles were source inspected by VEPCO and were received as part of the steam generator assembl No items of noncompliance or deviations were identifie.
Welding and Radiography Reivew of Main Steam Piping - ETA40007 Welding of the final joint in the main steam system of steam generator
"B" was observed. Two qualified welders were welding opposite each other and the weld was almost complete. Electrode stubs were disposed of in buckets. Preheat was maintained in the 400 -475° F rang Radiographs of main steam weld No. 1 D-4-U2A, were examined. This weld was 39.375" I. D. and was X-Rayed by the panoramic method to procedure RT-A-2-77-V A 5 1/2 minute exposure with an Iridium 192 source was use A No. 30 penetrameter was shown in an acceptable manner. This weld required additional grinding to be acceptable for the inservice inspection progra The radiography by TSL was in compliance with ASME Section V, 1974 Edition, Winter 1976 Addenda and with ASME Section III, 1974 Edition, Winter 1976 Addend The weld attaching the steam limiting device to the main steam nozzle of the "A" steam generator was examined. The weld which is a 1/2 11 fillet was made by CB It was subject to magnetic particle and visual inspection after clean-up and stress relie No items of noncompliance or deviations were identifie.
Steam Generator Girth Weld Radiograph Review The radiography for girth weld No. ETA 40006-PU-2A was examined to procedure RT-1, Revision A Cobalt 60 source of 92 curies was placed at the center of the steam generator and the films were arranged around the 0. D. of the weld. The material thickness was 3.7" and the focal film distance was about 7 feet. An exposure of 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />, 10 minutes using Kodak A-A film gave an acceptable density with a.010" lead screen in front of the film and a.020 11 lead in back of the film. The double film were processed in an automatic film processo There were 45 film (7 X 14 1/2) used and 12" of each film was rea There were six #50 penetrameters on the source side of the fil These films were acceptable and signed off by CBI, VEPCO, and the authorized Nuclear Inspector, (ANI) from Hartford Steam Boiler Insurance Compan No items of noncompliance or deviations were identified:.
- 3 -
'\\
- Feedwater Piping,Radiograph Review - ETA 40008 The feedwater nozzle radiography was qualified to procedure RT-9X Revision 1. The 3/8" thick thermal sleeve was in place when the radiography was done. The weld was made by the Shielded Metal Arc Method with the unfused root back-gouged and finish welded from the insid The radiographs for nozzle 30016-P-1-U2A were examined. The wall thickness was 4.75" and 9 films were exposed using a Cobalt 60 source and No. 45 penetrameter. The density of film was generally in the 2.82 range and the films were acceptabl An NCR No. 9574 was issued against the feedwater nozzle of the "A" steam generator. This NCR involved an under dimension in the I. and wall that is under evaluatio No items of noncompliance or deviations were identifie Exit Interview The inspector met with the individuals denoted in the Persons Contacted paragraph at the conclusion of the inspection on August 30, 1979. The inspector summarized the scope and findings of the inspection.
-
4 -