IR 05000280/1979004
| ML18113A961 | |
| Person / Time | |
|---|---|
| Site: | Surry |
| Issue date: | 02/13/1979 |
| From: | Herdt A, Wilcox J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML18113A960 | List: |
| References | |
| 50-280-79-04, 50-280-79-4, 50-281-79-04, 50-281-79-4, NUDOCS 7903280075 | |
| Download: ML18113A961 (3) | |
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UNITED STATES NUCLEAR REGULATORY COMMISSION
REGION II
101 MARIETTA STREET, ATLANTA, GEORGIA 30303 Report No.:
50-280/79-04 and 50-281/79-04 Licensee:
Virginia Electric and Power Company P. 0. Box 26666 Richmond, Virginia 23261 Facility Name:
Surry Power Station Units 1 and 2 Docket No.:
50-280 and 50-281 License No.:
DPR-32 and DPR-37 Inspection a~ri,; founty, Virginia Inspectorr,: ~,jt,~
tf. J ~ldr., Construction Inspector A.!il(; Her:dJ, ~hfef, Projects Section Approved by:
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A. R. Herdt, Chief Projects Section RC&ES Branch SUMMARY Inspection on January 15-19, 1979 Areas Inspected Date Signed J&1/y Dae Signed D~6-K?ia This special announced inspection involved 42 inspector-hours onsite in the area of steam generator replacement for Surry Power Station Units 1 and Results Of the areas inspected, no apparent items of noncompliance or deviations were identified.
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DETAILS Persons Contacted Virginia Electric and Power Company (VEPCO)
- * * ;';- ;', * * ;\\- * L. Stewart, Station Manager L. Parrish, III, Project Manager J. Kenny, Operations Coordinator B. Goodson, Resident QC Engineer W. Rhodes, Resident Engineer Construction P. Mangum, Jr., Resident Engineer Project Control F.Saunders, Advisory Engineer J. Rivas, Resident Engineer Construction Outside Containing W. Martin, Jr., Licensing and QA Department T. Benton, Director Production Technician Support Edmonds, Nuclear Training Coordinator L. Rentz, Resident QC Engineer D. Tower, VEPCO P. DeWandel, VEPCO C. Chamberlain, Senior Engineering Technician W. Gettler, Supervisor, Project Section, Civil Construction Daniel Construction Company (Daniels)
J. C. Ard, Project Manager T. Lawson, QC Manager Stone and Webster Engineering Corporation (S&W)
L. Viens, Head Site Engineering Office NRC Resident Inspector
- D. J. Burke
- Attended exit interview Exit Interview The inspection scope and findings were summarized on January 19, 1979, with those persons indicated in Paragraph 1 abov The scope of the inspection and the findings were reviewe The licensee was advised that no items of noncompliance were identified during this inspection.
- Licensee Action on Previous Inspection Findings Not Inspecte.
Unresolved Items.
Unresolved items are matters about which more information is required to determine whether they are acceptable or may involve noncompliance or deviation New unresolved items identified during this inspection are discussed in paragraph Steam Generator Replacement Code Requirements The inspectors reviewed the Safety Evaluation Report (SER) issued by the Office of Nuclear Reactor Regulatory dated December 15, 1978 and VEPCO's submittal to NRR dated August 1977 for the Surry Steam Generator Replacement (SSRG) thru Revision Paragraph 2. 3 of the SER under
"ASME Code and Regulatory Guide implementation" stated that all piping weld end preps, welding, and nondestructive examination will be in accordance with the applicable section of the latest edition of the AS.ME Cod Paragraph 2.9 of SSGR 2.9-1 Revision O, pertaining to VEPCO's Steam Generator Repair Program, implements the 1974 edition of the ASME Code,Section XI, including addenda through Winter 197 There appears to be a conflict between conflict between the SER and VEPCO's SSGR.2.9-1 since the latest edition and addenda is not the Winter 1976. This was identified as an unresolved item "ASME Code Requirements" and will be identified as 280-281/79-04-0 Independent Inspection The inspectors reviewed VEPCO, Daniels, and Stone and Webster (S&W)
Steam Generator replacement project organization The schedule and numerous Engineering Task Assignments (ETA) relating to the Steam Generator replacement project were reviewe The general overall project schedule was reviewed with the licensee; also included was a video tape and oral presentation by VEPCO to the NRC RII personnel presen The inspectors conducted an inspection of the site to which included the following areas: warehouse facilities; unloading dock and routes of new steam generators being transported; piping mock-up area; welding qualification area; storage area for the old lower steam gener-ator shells; and the new pipe refurbishment buildin The licensee is scheduling to commence this replacement on January 26, 197 It was noted that all staffing requirements have not yet been completed, and the licensee assured that this would occur prior to commencement of the actual Steam Generator replacemen No items of noncompliance or deviations were noted as a result of this inspection.