IR 05000281/1979038
| ML18130A488 | |
| Person / Time | |
|---|---|
| Site: | Surry  |
| Issue date: | 06/11/1979 |
| From: | Bryant J, Wilcox J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML18130A481 | List: |
| References | |
| 50-281-79-38, NUDOCS 7908240168 | |
| Download: ML18130A488 (3) | |
Text
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Report No. 50-281/79-38 UNITED STATES NUCLEAR REGULATORY COMMISSION
REGION II
101 MARIETTA ST., N.W., SUITE 3100 ATLANTA, GEORGIA 30303 Licensee:
Virginia Electric and Power Company Richmond, Virginia 23261 Facility Name:
Surry Power Station Unit No. 2 Docket No. 50-281 License No. DPR-37 Inspection site near Wil iamsburg, Virginia SUMMARY Inspection on May 22-25, 1979 Areas Inspected Date Signed Date Signed This routine, unannounced inspection involved twenty-two inspector-hours onsite in the areas of construction status, engineering task assignments (ETA) review, licensee action on previous inspection findings, and observation of helicoil replacement on the steam generator fee Results Of the four areas inspected, no apparent items of noncompliance or deviations were identified in three areas; one apparent item of noncompliance was found in one areas (Deficiency -
steam generator support feet helicoil replacement -
paragraph Sc).
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DETAILS Persons Contacted Licensee Employees
- W. L. Stewart, Station Manager
- R. F. Saunders, Superintendent, Maintenance
- T. A. Peebles, Superintendent, Technical Services
- R. F. Baldwin, Supervisor, Administrative Services
- F. L. Rentz, Resident QC Engineer
- C. W. Rhodes, Resident Engineer, Construction SGRP
- E. P. Dewandel, Staff Assistant
- W.R. Skelley, Jr., Staff Assistant SGRP
- T. J. Kenny, Engineer Supervisor, SGRP Outage Coordinator C. Boggess, Shipping & Receiving Superintendent M. Randolph, Construction Engineer A. L. Parrish, III, SGRP Manager Other licensee employees contacted included two technicians, three mechanics, two security force members, and four office personne Other organizations T. O'Hara, Site Representative, Westinghouse (W)
F. Smith, Engineering Manager, Daniels Construction Company (Daniels)
T. Lawson, Q. C. Manager, Daniels Construction Company (Daniels)
NRC Resident Inspector
- D. K. Burke
- Attended exit interview Exit Interview The inspection scope and findings were summarized on May 25, 1979 with those persons indicated in Paragraph 1 abov The scope of the inspection was discusse The deficiency concerning helicoil replacement on the steam generator feet was discussed in detai Licensee Action on Previous Inspection Findings (Closed) Deviation (281/79-14-01); "Inadequate records - nitrogen purge of S.G. lower assembl A followup inspection was made on the VEPCO response dated April 19, 197 This inspection ensured that all corrective steps stated in the response had been perform on the records to S. G. lower assemblies identified as #2927, #9273 & #298 These records are adequate
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-2-and are being maintained in accordance with Westinghouse NPT 91, 94 and VEPCO quality assurance procedures. This item is close.
Unresolved Items Unresolved items were not identified during this inspectio.
Independent Inspection Effort Construction Status Portions of the reactor coolant (RC) p1p1ng are being decontaminated for weld preparation and end prep machinin Machine weld prep of "C Cubicle" RC pipe on the valve end and on the pump end are being accomplishe Due to the reworking and NDE of lower shell S. supports there has been some delay in the reinstallation of the new lower shell Engineering Task Assignments (ETA)
The inspector examined the following VEPCO ETA' s for completeness, sign-offs, dates, and documentation:
ETA fl 20027 30007 Title Polar Crane Misc Procedure (Load Test & Index)
Cutting Feedwater Piping The ETA's reviewed were found to be handled and documented in a thorough and objective manne No item of noncompliance or deviations were identified in the above area inspecte Observation of Helicoil Replacement on the Steam Generator Feet The inspector observed Daniels mechanics replacing several helicoils in the new steam generator lower assembly support feet. It was noted that the mechanics were working under the authority of a VEPCO furnished speed letter with attached instruction for a proc~dure to replace the helicoils. These instructions were issued by the cognizant responsible engineer with stated Westinghouse approva The task of replacing the helicoils was within the capabilities of the mechanics performing the work and the instructions were technically satisfactory. However, the instructions were not issued nor approved in the manner specified by VEPCOs Nuclear Power Station Quality Assurance Manual. This is identi-fied as deficiency 281/79-38-01, "Steam Generator Support Feet - Helicoil Replacement".