IR 05000361/1979012
| ML13309A706 | |
| Person / Time | |
|---|---|
| Site: | San Onofre  |
| Issue date: | 05/31/1979 |
| From: | Dodds R, Pate R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V) |
| To: | |
| Shared Package | |
| ML13309A705 | List: |
| References | |
| 50-361-79-12, 50-362-79-12, NUDOCS 7907260978 | |
| Download: ML13309A706 (4) | |
Text
U. S. NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT
REGION V
50 361/79-12 sNo. 50-362/79-12 TOb T ~~~~~~~~
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CPPR-97 mi ease No, 50-362 Priority CPPR-98 Category c ensee Southern California Edison Company 2244 Walnut Grove Avenue Rosemead, California 91770 F
ty Name San Onofre Units 2 and 3
cji~on at, Construction Site, San Diego County, California
- in Pection conducted-April 1-30, 1979 Inspzac ors:
___
~
7 R. J. Pate, Resident Reactor Inspector Date Signed Date Signed Date Signed Anoxoved hV t LVJ R. T. Dodds, Chief, Engineering Support Section,'
1ate signed Reactor Construction and Engineering Support Branch Summary:
Inspection on April 1-30, 1979 (Report Nos. 50-361/79-12 and 50-362/79-12)
Areas Inspected:
Routine, unannounced inspection by the resident inspector of construction activities including: piping storage, fit-up, welding and nondestructive testing; reactor pressure vessel and internals protection; storage of safety related control valves; licensee corrective actions on previous inspection findings; and general work in progress. The inspection involved 52 inspector-hours onsite by one NRC inspecto Results: Of the five areas inspected, no items of noncompliance or deviations were identifie IE:V Form 219(1)
7907280 96
DETAILS 1. Individuals Contacted a. Southern California Edison Company (SCE)
+=P. A. Croy, Site Quality Assurance/Quality Control Supervisor R. Frick, Quality Assurance Engineer
+= D. Hamlin, Project Manager
+=*R. R. Hart, Construction Superintendent J..Huey, Quality Assurance Engineer P. R. King, QA Engineer
+=H. S. Leasure, Chief, Contract Construction Management
+=D. E. Nunn, Manager, Quality Assurance J. J. Pantaleo, Quality Assurance Engineer F. Pimentel, Quality Assurance Engineer
+H. B. Ray, Project Management
+*L. L. Seyler, Project Quality Assurance Supervisor M. Rodin, Quality Assurance Engineer
+*W. F. Rossfeld, Quality Assurance Engineer
=*D. B. Schone, Lead Engineering Site Representative L. D. Tipton, Nuclear Engineering Site Representative Bechtel Power Corporation (Bechtel)
=J. E. Bashore, Division Quality Assurance Manager
+=*C. A. Blum, Quality Control Manager
=*J. R. Caldwell, Project QA Supervisor
+=R. H. Cutler, Project Field Engineer
+=*J. E. Geiger, Project Field Quality Assurance. Supervilsor
+W. D. Nichols, Assistant Prjoect Field Engineer
+S. S. Ortega, Project Quality Assurance Engineer In addition, construction craftsmen, engineers and foremen were contacted during the inspectio *Denotes attendees at management meeting on April 12, 197 Denotes attendees at management meeting on April 20, 197 +Denotes attendees at management meeting on April 27, 197. Construction Status The licensee reported that site construction work is 66% complete as of April 26, 1979. The licensee's project management personnel estimate that the construction effort is split 60%/40% between Units 2 and.
Licensee Action on Previous Inspection Findings The inspector examined the action taken by the licensee on the following outstanding ite (Closed) Unresolved Item (50 361/79-06/02): The inspector found that some cable trays contained spray-on insulation that had fallen into the trays when the insulation was applied to the ceiling above the tray The licensee examined the possible affects the insulation could have on the cables and could identify no detrimental affects. The licensee stated that all power cables are derated to allow for passing through fire barriers and/or for being installed in covered trays. This derating is sufficient to accommodate the spray-on insulation coating the. cables in the trays. The inspector had. no additional questi.on. Reactor Vessel and Internals Storage Site activities for storage of the Unit 2 and 3 reactor pressure vessels and internals were observed. Both vessels are installed and installation of Unit 2 internals is essentially complet Installation of Unit 3 internals was recently initiated. The contractor was controlling access to the equipment and maintaining protective covers as required by the construction procedures. Tool control was being maintained during all operations where access would be difficult subsequent to installation of the internal No item of noncompliance or deviations were identifie. Reactor Coolant Pressure Boundary and Safety Related Piping The piping related activities listed below were observed to ascertain compliance with applicable construction specifications and procedure Activity System Identification N Pipe Fitup Safety Injection S2-1204-ML-145 Sh.1 Weld BA Pipe Storage Safety Injection S3-SI-075-2B Pipe Handling Safety Injection S2-SI-077-3B S Radiograph Reactor Coolant S3-1201-ML-003 Weld D Liquid Penetrant Exam Reactor Coolant S3-1201-ML-006 Sh.1 Weld D Pipe Welding Reactor Coolant S3.-1201-ML-006 Weld D
- Pipe Welding Safety Injection S2-1204-ML-145 Sh.l Weld BA No items of noncompliance or deviations were identifie. Safety Related Equipment (Valves)
The storage of safety related control valves at the construction site was examined. The inspector found that the storage requirements of ANSI N45.2.2 were not being followed after the valves were moved to the job site for installation. This time period was normally expected to be relatively short (1 to 2 weeks) and therefore, had not been considered by the licensee or constructor to be a storage activity, but instead was considered an installation activity. However, due to design changes and insufficient planning, some of the valves had been at the job site for several months. The licensee has issue corrective action requests (CAR's) to the constructor to upgrade the on-site conditions to meet the requirements.of ANSI N45. The target date for implementing the new on-site storage procedures is June 15, 1979. Immediate action was taken to move the control valves not being installed back to the controlled storage area in the warehouse. The inspector did not have any additional question This area will be inspected again during a future inspection (50-361/79-12/01).
7. Plant Tour The inspector toured both Units 2 and 3 several times each week during the inspection report period. Particular attention was directed to observing work in progress, availability of supervision and quality control inspectors at the work areas, housekeeping, and preservation of equipmen No items of noncompliance or deviations were identifie. Management Interview The inspector met with the licensee representatives (denoted in Paragraph 1) on April 12, 20 and 27, 1979. The scope of the inspections and inspector's findings as noted in this report were discusse The licensee representatives had no additional comments.