IR 05000546/1979020
| ML19254F528 | |
| Person / Time | |
|---|---|
| Site: | Marble Hill |
| Issue date: | 10/04/1979 |
| From: | Danielson D, Erb C NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | |
| Shared Package | |
| ML19254F523 | List: |
| References | |
| 50-546-79-20, 50-547-79-20, NUDOCS 7911090578 | |
| Download: ML19254F528 (3) | |
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U.S. NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT
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REGION III
Report No. 50-546/79-20; 50-547/79-20 Docket No. 50-546; 50-547 License No. CPPR-170; CPPR-171 Licensee:
Public Service of Indiana 1000 East Main Street Plainfield, IN 46168 Facility Name: Marble Hill Generating Station, Units 1 and 2 Inspection At: Marble Hill Site, Jefferson County, Indiana Inspection Conducted:
September 20-21, 1979
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Approved By:
D. H. Danielson, Chief
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Inspection Summary Inspection on September 20-21, 1979 (Report No. 50-546/79-20; 50-547/79-20)
Areas Inspected: Assembly of jacking tower preparatory to 110% overload test for the reactor vessel (Unit 2); procedures for lifting reactor vessel; storage of safety related equipment (Unit 1).
The inspection involved a total of 12 inspector-hours on site by one NRC inspector.
Results: No items of noncompliance or deviations were found.
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DETAILS Persons Contacted Public Service of Indiana (PSI)
- R. M. Brown, Construction Project Superintendent
- T. L. McLarty, Quality Assurance Construction Supervisor
- G. Weston, Quality Control Engineer
- Denotes those present during the exit interview.
Functional or Program Areas Inspected On August 7, 1979, PSI ordered all safety related activities on the Marble Hill site be stopped. Receiving of safety related equipment will continue, but will be limited to verification of receipt of order and transportation damage. Certain non-safety related activities are continuing on site, with over 500 production craft people at work.
1.
Review of Overload Test Activities The inspector reviewed QCX-9, Revision 1, which is the Load Testing Procedure for the Jack Tower. This load test will be performed by Aycock Inc. and apply to the Unit No. 2 reactor pressure vessel which weighs 334.3 tons. The test load will consist of concrete slabs, which were checked out at 367.8 tons. The structure and the four jacks that are used to lift the vessel from the Schnable railroad car, were positioned in place. Since it rained heavily Thursday night and Friday, it was decided to suspend the lifting of the vessel until the following week.
Procedure QCX-22, Off-Loading Reactor Pressure Vessel, was examined and a hold point with signature after step 4.22 was suggested by the inspector and agreed to by the licensee.
No items of noncompliance or deviations were identified.
2.
Survey of Containment-Units 1 and 2 There was water in both containments and threaded floor bolts in several places were almost submerged. Some materials should be removed and pumping will be required in both containments.
This is an unresolved item that will be checked during a future inspection.
(50-546/79-20-01; 50-547/79-20-01)
3.
Storage a.
A field corrective action request FCAR No. 364-79 has been issued on the Unit I reactor pressure vessel, due to evidence
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of rusting on the "0"-ring area of vessel flange. A recommendation for corrective action has been requested from Westinghouse, the supplier.
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The reactor pressure vessel seal ring, which was still on the freight car, contained water in two corners of the plastic wrap, due to damage to the plastic.
This was noted by the licensee QC engineer. The ring is to be unpacked and inspected immediately.
c.
Several pieces of Main Steam System piping were lying near a pile of jack tower testing concrete overload slabs.
While coarse gravel had been spread in the area, the ground would not support concentrated heavy loads. Dunnage was under the pipe, but it did not appear that the pipe would clear ground level especially after a rain. A 32-inch Class 2 Main Steam piping spool, MHIMS01AB,was found in this area with one end protector lying beside it.
The licensee QC engineer took steps to have the protector reattached to the pipe.
No items of noncomplianta or deviations were identified in this area.
Unresolved Items
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Unresolved items are matters about which more information is required in order to ascertain whether they are acceptable items, items of noncompliance, or deviations. An unresolved item disclosed during the inspection is discussed in Paragraph 2.
Exit Meeting The inspector met with licensee representatives (denoted in the Persons Contacted paragraph) at the conclusion of the inspection on September 21, 1979. The inspector summarized the scope and findings of the inspection, which were acknowledged by the licensee.
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