IR 05000546/1981007
| ML20004E576 | |
| Person / Time | |
|---|---|
| Site: | Marble Hill |
| Issue date: | 05/28/1981 |
| From: | Danielson D, Erb C NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | |
| Shared Package | |
| ML20004E573 | List: |
| References | |
| 50-546-81-07, 50-546-81-7, 50-547-81-07, 50-547-81-7, NUDOCS 8106120353 | |
| Download: ML20004E576 (3) | |
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O U.S. NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT
REGION III
Report Nos. 50-546/81-07; 50-547/81-07 Docket Nos. 50-546; 50-547 License Nos. CPPR-170, CPPR-171 Licensee: Public Service of Indiana
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P. O. Box 190 New Washington, IN 47162 Facility Name: Marble Hill Nuclear Jenerating Station, Units 1 and 2 Inspection At: Marble Hill Site, Jefferson County, IN Inspection Conducted: April 27-29, 1981 U
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Inspector:
'C. M. Erb
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Approved By:
D. H. Danielson, Chief
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Materials and Processes
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Section Inspection Summary Inspection on April 27-29, 1981 (Report Nos. 50-546/81-07; 50-547/81-07)
Areas Inspected: Followup on previously identified inspection findings and licensee action relative to 50.55(e) reported items. This inspection involved a total of 20 inspector-hours onsite by one NRC inspector.
Results: No items of noncompliance or deviations were identified.
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O DETAILS Public Service of Indiana (PSI)
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- L. O. Ramsett, QA Manager
- S. J. Brewer, Nuclear Safety and Licensing Manager
- T. D. lieib, Nuclear Safety and Licensing
- R. D. Crouch, QA Verification Records Supervisor
- J.
K. Wolfe, QA Administrative Assistant
- C. G. Beckham, Quality Engineer
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- J. M. Roberts, Quality Assurance
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S. H. Shuter, Quality Engineer - Civil J. Parks, Welding Superintendent & NDE for QA Other Personnel C. Jergens, QC Engineer, Cherne A. Dolgaard, QA Manager, Cherne
- Denotes those present at the exit interview.
Licensee Action on Previously Identified Items 1.
(Closed) 50.55(e) Item (546/79-EE-02) Tower Crane Damage to Containment Liner On April 6, 1979, two construction cranes collided, with the counter-weight of a tower crane striking the jib of a Model 4100 crane, which then fell and struck the outside of the containment liner.
Damage to the liner and reinforcement occurred in two places. At elevation 525 feet one vertical angle stiffener and the circular C8 ring stiffener were damaged. At approximate elevation 464 feet, three #11 vertical and six #11 horizontal reinforcing bars were damaged.
As a result of this incident, the damaged reinforcing bars were replaced and the circular ring stiffener and vertical angle stiffeners were repaired. Templates were used to check deforma-tion in the liner plate and an MT inspection was conducted of welds in the area. A damaged tendon sheath was cut and a connector installed to replace the dented length. A rabbit was then passed through the sheath to assure an opening for the tendon placement.
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The various repair steps outlined by S&L have been performed and verified by the inspector. This ites is resolved.
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(Closed) 50.55(e) Item (546/80-EE-15) Lakeside Bridge and Steel Company (LB&SCo) - Repair and Reradiography of Steam Generator Upper Lateral Support Embedments and Pipe Restraints-2-
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Density of radiographs of the welds in subject parts were found to be nonconforming to ASME Section V Code by Lakeside Bridge and Steel Company. The parts were returned and at that time certain welds were found to contain deficient areas. The parts requiring repair welding were repaired and reradiographed at the LB&SCo facility. These items were inspected to the requirements of ASME Section III, Subsection NF, 1974 Edition, Summer 1975 Addenda.
Due to configuration of weld's No. 50 and 52, only 8 inches of the 32-X series parts could be radiographed. Radiography was performed to LB&SCo Procedure 7.10, Revision 2.
The remaining 3 inches of the weld.was volumetrically inspected using ultrasonics. The inspector examined the 40 series-embeds and the 32 series reactor coolant pipe restraints and found the welds to be acceptable to Code.
The docementation indicates all required radiography and repair welding to have been accomplished. This item is resolved.
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(Closed) 50.55(e) Item (546/79-EE-08) Lack of Procedure for Welding 3/4 inch Reactor' Coolant Pipe Lines This item was reported because the weld procedure for the socket welds made in two 3/4 inch stainless steel drain off lines from the reactor vessel head area was deficient. The two lines were scrapped and fabrication of two replacement lines was performed using weld procedure 808B022-0.56CT. Prosc ?.re No.13.10 was used for alignment and to insure the proper gap at the bottom of the socket joint. A Penetrant Test to procedure No. 14.2.12.76 was i
l used to check the welds. The hydro test of the lines has not occurred, but will be performed before the lines are encased t
in concrete. This item is resolved.
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(Open) Unresolved Item (546/80-23-03; 547/80-23-03) Small Hydraulic and Air Lines Rusting and Other Deficient Items v
Work is beginning on the two Polar Cranes. Certain welds are being reworked and a check will be made on electrical items, which were not protected from the weather. The hydraulic lines are still open in some cases, and it appears replacement must be made, since some inside rusting was reported. This item remains open.
Exit Interview l
The inspector met with licensee representatives (denoted in Persons Contacted paragraph) on April 29, 1981. The inspector summarized the
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purpose and findings of the inspection, which were acknowledged by the
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licensee.
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