ML20024B118
| ML20024B118 | |
| Person / Time | |
|---|---|
| Site: | River Bend  |
| Issue date: | 06/24/1983 |
| From: | Booker J GULF STATES UTILITIES CO. |
| To: | Jay Collins NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| References | |
| 10CFR-050.55E, 10CFR-50.55E, DR-104, RGB-15-332, NUDOCS 8307050238 | |
| Download: ML20024B118 (2) | |
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es GULF STATES UTILITIES COMPANY POST OFFICE BOX 2951
- BEAUMONT. TEXAS 77704 AREA CODE 713 838-6631 June 24, 1983 RBG-15,332 File Nos. G9.5, G9.25.1.1 Mr. John T. Collins, Regional Administrator I [M @ hk[;... -
U. S. Nuclear Regulatory Commission Region IV, Office of Inspection and Enforcement 611 Ryan Plaza Drive, Suite 1000 f~
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Ar1ington, Texas 76011 l J/
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Dear Mr. Collins:
River Bend Station Unit 1 Docket No. 50-458 Final Report /DR-104 On March 28, 1983, Gulf States Utilities Company (GSU) notified Region IV of a condition potentially reportable under 10CFR50.55(e) concerning the overturning of the Transilift Crane that was lifting the Reactor Shield Building dome (DR-104). GSU subsequently issued an Interim Report dated April 28, 1983.
GSU notified Region IV on June 22, 1983 by telephone it would consider this deficiency as reportable under 10CFR50.55(e). The attachment to this letter is GSU's final written report pursuant 10CFR50.55(e)(3). This concludes GSU's response on this item.
Sincerely, J. E. Booker Manager-Engineering, Nuclear Fuels & Licensing River Bend Nuclear Group JE PJD/kt cc: Director of Inspection & Enforcement U. S. Nuclear Regulatory Commission Washington, D. C. 20555 R. L. Brown (SRI) h~
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8307050230 830624 PDR ADOCK 05000458 g
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RBG-15,332 ATTACHMENT DR-104/ Reactor Shield Building Dome Concrete Traming Assembly and Crane Accident i
Description of the Deficiency i
l At approximately 7:30 p.m. on March 25,.1983 while lifting a 400 ton form for the Reactor Shield Building dome at River Bend Station, the Transi-lift Crane (leased from Niel F..Lampson, Inc.) collapsed allowing the framing assembly to fall. Components of the dome concrete framing 1
ll assembly were extensively damaged. Several vehicles and construction buildings were damaged.
However, no plant structures or any permanent plant equipment were damaged.
j Safety Implications j
Had the condition described above remained uncorrected, j
correct installation of the dome framing assembly would'not have been possible due to the extent of the damage.
Corrective Action i
I All damaged areas of the Reactor Shield Building dome concrete framing assembly will be replaced, or inspections will be performed to ensure that undamaged pieces to be reused are acceptable. The dome will be erected in place; i
another attempt to lift it in one piece will not be made.
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