IR 05000280/1979050
| ML18136A220 | |
| Person / Time | |
|---|---|
| Site: | Surry  |
| Issue date: | 09/11/1979 |
| From: | Crowley B, Herdt A NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML18136A215 | List: |
| References | |
| 50-280-79-50, 50-281-79-70, NUDOCS 7911260180 | |
| Download: ML18136A220 (4) | |
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L UNITED STATES NUCLEAR REGULATORY COMMISSION
REGION II
101 MARIETTA ST., N.W., SUITE 3100 ATLANTA, GEORGIA 30303 Report Nos. 50-280/79-50 and 50-281/79-70 Licensee: Virginia Electric and Power Company Richmond, Virginia 23261 Facility Name: Surry Nuclear Plant Docket Nos. 50-280 and 50-281 License Nos. DPR-32 and DPR-37 SUMMARY Insp~ction on August 27-29,1979 Areas Inspected Virginia Dateign f/t}7f Date Signed This routine, unannounced inspection involved 20 inspector-hours onsite in the area of steam generator feedwater line radiography (RT) and repai Results In the one area inspected, one item of noncompliance was found (Failure to follow radiography procedure-Paragraph 5).
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, Persons Contacted Licensee Employees
- W. L. Stewart, Station Manager DETAILS
- * * * Peebles, Superintendent of Technical Services Saunders, Maintenance Superintendent Maciejewski, Engineering Supervisor (NDT)
Rentz, Resident QC Engineer
- E. P. Dewandel, Staff Assistant T. w. Brombach, NDE Foreman M. w. Kight, Welding Foreman Other licensee employees contacted included two construction craftsmen, two security force members and various office personne NRC Resident Inspector
- D. J. Burke
- Attended exit intervie.
Exit Interview The inspection scope and findings were summarized on August. 29, 1979 with those persons indicated in Paragraph 1 abov The noncompliance of para-graph S.a. was discussed and the licensee stated that an independent review was being made of all radiographs and reradiography would be performed where necessar.
Licensee Action on Previous Inspection Findings Not inspecte.
Unresolved Items Unresolved items were not identified during this inspectio IE Bulletins (IEB)
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(Open) IEB 79-13, Cracking in Feedwater System Piping, Units 1 and The inspector performed a followup inspection of radiography and subsequent weld repairs which were performed to meet the Bulletin requirement The inspection consisted of the following: RT Film Review Radiography was performed in accordance with VEPCO Procedure NDT-10.1,
- "Radiographic Inspection of Pipe and Plate Welds" except that evalua-tion was to the 1977 ~~ition of AS~, Section lfl, Sijpsection NC, paragra~h;,~-50.PP to ~~e: 27 quJH~y' leve,
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-2-Unit 1 At the time of the film review all radiography had been complete However, welds 3 and 4 on line 14"WFD-17 had been cut out to replace an elbow which had a base material defect detected during repair of weld RT film for the following welds; which included the new welds made to replace the cracked reducer, all repair welds, and a sample of other welds; were reviewed:
Loop A Loop B Loop C Weld 18A*
Weld 5*
Weld 15 Weld 5 Weld 6 Weld 9 Weld 11*
Weld 13*
Weld 8 Weld 10 During review of the above film, the inspector noted that. for the welds noted with an asterisk the film density in the area of interest was more than 30 percent darker than the density through the penetra-mete Paragraph 7.12.1.1 of VEPCO procedure NDT-10.1 states in part,
"If the density of the *radiograph anywhere through the area of interest varies by more than minus 15, plus 30 percent then an additional penetrameter shall be used for each exceptional area or*areas.*. "
This failure to follow procedure is considered to be noncompliance.
with section 6.4.D of the Surry Power Station Technical Specifications and is identified as item number 280/79-50-01, "Failure to Follow Radiography Procedure".
Unit 2 The RT effort on Unit 2 had just starte The following Loop A.film were reviewed:
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Weld 9 Weld 6 Weld 7 Weld 5-3-Welds 6 and 9 were acceptabl Welds 5 and 7 were rejected for porosit Observation of Welding (Unit 1)
The inspector observed in-process welding on welds 3A and 4A (replacement welds for 3 and 4) of Loop "A".
These welds were being made to replace the defective elbow (see paragraph Sa. above).
In addition to observing the in-process welding, the "Weld Traveler",
"Corrective Maintenance Procedure" MMP-C-G-077, and applicable
"Welding Operator Qualifications Tests" were reviewe The welding was being accomplished in accordance with.specification USAS B31.1.0, 1967 Editio *
Within the areas in~pected, one item of noncompliance as noted in paragraph Sa. above was identifie /
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