IR 05000281/1979039
| ML18130A478 | |
| Person / Time | |
|---|---|
| Site: | Surry  |
| Issue date: | 07/06/1979 |
| From: | Cantrell F, Gouge M NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML18130A477 | List: |
| References | |
| 50-281-79-39, NUDOCS 7908230691 | |
| Download: ML18130A478 (4) | |
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UNITED STATES NUCLEAR REGULATORY COMMISSION
REGION II
Report No. 50-281/79-39 101 MARIETTA ST., N.W., SUITE 3100 ATLANTA, GEORGIA 30303 Licensee:
Virginia Electric and Power Company Richmond, Virginia 23261 Facility Name: Surry Unit 2 Docket No. 50-281 License No. DPR-37 Inspection at Surry Site nea/l~lliamsburg, Virginia Inspector:M. J. Goug~~~"f;"=="
Approved by: ~~
F. S. antreIT; Acting e ~
Chief, RCES Branch SUMMARY Inspection on June 19-22, 1979 Areas Inspected Date Signed
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This routine, unannounced inspection involved 24 inspector-hours on-site in the areas of steam generator replacement program QA audits, control of nonconformance reports, and observation of welding activitie Results Of the three areas inspected, no apparent items of noncompliance or deviations were identified.
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DETAILS Persons Contacted Licensee Employees
- W. L. Stewart, Station Manager
- C. W. Rhodes, Resident Engineer Construction (SGRP)
C. W. Embler, Staff Engineer, Welding (SGRP)
R. Bradshaw, QA Engineer (SGRP)
Y. P. Mangum, Jr., Resident Engineer Project Control (SGRP)
Other licensee employees contacted included various construction craftsmen, technicians., and off ice personne Other Organizations Daniel Construction Company (DCC)
J. Latimer, Project Welding Engineer NRC Resident Inspector
- D. J. Burke
- Attended exit interview Exit Interview The inspection scope and findings were summarized on June 22, 1979 with those persons indicated in Paragraph 1 abov.
Licensee Action on Previous Inspection Findings Not inspecte.
Unresolved Items Unresolved items were not identified during this inspectio.
Independent Inspection Effort a *
Steam Generator Replacement Program Quality Assurance (QA) Audits Audit procedures for Surry Power Station are specified in section 18 of the Nuclear Power Station Quality Assurance Manual (NPSQAM).
A QA local instruction, "Monitoring Audit Activities," has been issued to augment the NPSQAM and to meet the special requirements of the Steam Generator Replacement Project (SGRP).
This local instruction was
- approved May 14, 1979 and was used for the performance of audits during the period May-June 197 The Region II inspector reviewed audit checklists, audit findings and project responses for monitoring audits conducted during the period May-June 197 The monthly written summary of audits conducted, findings, and audits planned was reviewe The inspector attended the monthly critique of audit findings and QA
_ trends that the resident QC engineer held with SGRP managemen The SGRP audit schedule for 1979 was reviewed for completenes The SGRP audit program was being conducted in accordance with the QA local instruction, "Monitoring Audit Activities."
No items of noncompliance or deviations were identifie Control of Nonconformance Reports (NCR's)
Control of NCR's is described in the Surry NPSQAM, Section 15s, Revision 1, Nonconformances (SGRP).
Open NCR's 79-31 through 79-189 were reviewed for conformance to the above procedur Closed NCR's through 79-90 were reviewed for acceptable dispositio All NCR's reviewed had been documented and controlled in accordance with the above pro-cedur The Quality Assurance unit is reviewing all open NCR's in an effort to resolve NCR's in a timely manne The QA unit also reviews all NCR's for acceptable disposition and to determine if any signifi-cant trends are developing in the SGR No items of noncompliance or deviations were identifie.
Steam Generator Replacement Observation of Welding and Associated Activities The applicable code as required by VEPCO'S licensee submittal (Steam Gen-erator Project Surry Power Station Unit Nos. 1 and 2, Revision 9), is ASME Section XI, 1974 Edition with Addena through the Winter of 197 Based on paragraph IWA-7000 of section XI, VEPCO is using the original construction code (USAS B31.1.0-1967) for pipe weldin Welder qualifications and procedure qualifications are being performed in accordance with the latest edition and addenda of ASME section IX in effect at the time of qualifica-tion. All welding materials were purchased and certified in accordance with Class I requirements of the ASME cod *
The inspector observed in process welding of reactor coolant piping EP-4B joining loop B cold leg to steam generator B nozzl Areas inspected included identification and documentation of QC hold points, proper preheat and interpass temperature, welder qualification to the procedure 8-8-B-22 (automatic TIG), welding technique, and the certified material test report (CMTR) for the welding filler material Welding was conducted in accor-dance with procedure 8-8-B-22 by qu~lified welder The controlled weld joint record identified QC hold points and these hold points had been properly documente The CMTR for welding filler material heat number Y4070L308 met the chemical requirements specified in SFA 5.9 Section II, Part C of the 1974 ASME code through Winter 1976 addenda for ER-308 materia *
-3-The Region II inspector observed the second repair to reactor coolant piping section EP-SA (weld #2).
Areas inspected included proper docu-mentation of the basic weld buildup and subsequent repairs, welder qualification to applicable procedures, welding technique, control of interpass temperature, and the CMTR for the welding filler material The basic weld buildup on weld #2 of EP-SA, repair 1 and repair 2 had been documented properl The welder performing repair 2 was qualified to procedure 8-8-B-9, Rev. 0 for the thickness he was allowed to wel Interpass temperature was properly controlle The CMTR for welding filler material heat number 762904 (ER-3161) was reviewe The CMTR met the chemical requirements for ER-3161 material specified in SFA 5.9 referenced abov No items of noncompliance or deviations were identified.