ML20087G410
| ML20087G410 | |
| Person / Time | |
|---|---|
| Site: | Hatch  |
| Issue date: | 03/12/1984 |
| From: | Gucwa L GEORGIA POWER CO. |
| To: | Stolz J Office of Nuclear Reactor Regulation |
| References | |
| REF-GTECI-A-36, REF-GTECI-SF, RTR-NUREG-0612, RTR-NUREG-612, TASK-A-36, TASK-OR NED-84-129, TAC-47007, TAC-47008, NUDOCS 8403200005 | |
| Download: ML20087G410 (2) | |
Text
Gawgia Pw<er Company e
333 P:edmont Avenue Atlanta, Georg a 30308 Telephor.o 404 5266520 Meng A$jress Post Office Box 4'AS Atlanta Georgta 30302 Georgia Power L T. Cucwa Itw sour **sn ei otoc system t
uanaae: Nuc*a' En9'neann9 STI)-84-129 and Ctwf Nuclear Eng.nwr March 12, 1984 Director of Nuclear Reactor Regulation Attention: Mr. John F. Stolz, Chief Ope ating Reactors Branch No. 4 Division of Licensing U. S. Nuclear Regulatory Cmmission Wathington, D. C.
20555 NRC DOCKETS 50-321, 50-366 OPERATING LICENSES DPR-57, NPF-5 HEIN I. HATCH NUCLEAR PLANT UNITS 1, 2 NUREG-0612, "CONIROL OF HEAW IIRDS AT NUCLFM POWER PLANTS" Gentlenen:
A telephone conference involving representatives of the NRC and Georgia Power Cmpany (GPC) took place on February 29, 1984.
'Ihe subject of the discussion was the design of certain overhead cranes at Plant Hatch relative to the guidelines of NUREG-0612.
At the request of the NRC, additional action has been taken to verify certain aspects of overhead crane design at Plant Hatch.
Guideline 7 of NUREG-0612 specifies that the design of overhead cranes should emply with the intent of CMAA Specification 70, " Specifications for Electric Overhead Travelling Cranes".
The Plant Hatch Units 1 and 2
~
(HNP-1&2) Reactor Building Overhead Cranes and the HNP-1 Turbine Building Overhead Crane, which were not designed to CMAA-70, were evaluated in our July 29, 1983 subnittal with respect to the CNAA-70 requirements and shown to be equivalent in all areas where design data were available.
Data were not available, however, to confirm that drm design, drm groove depth and pitch, and gearbox design met the requirenents of CMAA-70.
These three design aspects were the specific subjects of the February 29, 1984 4
discussion.
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Georgia Power d Director of Nuclear Reactor Regulation Attention: Mr. John F. Stolz, Chief Operating Reactors Branch No. 4 March 12, 1984 Pace 'No the following facts should reove any doubt as to the quality of the design of the cmponents in question:
1.
The cranes in question, including the drms and drm gearboxes, were manufactured in their entirety by P&H Harnischfeger, which is a leader in the industry. The manufacturer was closely involved in the developnent of CMAA-70.
2.
A cmparison of EOCI-61, the standard to which the cranes were designed and manufactured, with CNAA-70 showed that all other cmponents evaluated on the cranes were of an equal or greater quality level than required by CMAA-70.
Furthermore, the rquirments for drm and gearbox design included in CNAA-70 were merely a codification of good engineering and industrial practices in place at the time the Hatch cranes were manufactured.
3.
'Ihe cranes in question have been in use approximately nine to ten years with no significant probles. This provides strong assurance that the entire cranes were designed and manufactured to meet the rquired service conditions.
Based on the above, it is our position that the HNP-3&2 Reactor Building Overhead Cranes and the HNP-1 Turbine Building Overhead Crane cmply with the intent of CMAA-70 and as such satisfy today's-standards relative to crane safety and reliability.
Please contact this office if there are any questions.
Very truly yours,
/f k' =
L. T. Gucwa JHAnb xc:
J. T. Beckham, Jr.
H. C. Nix, Jr.
P. D. Rice J. P. O'Reilly (NRC-Region II)
Senior Resident Inspector rwns