ML20010J003
| ML20010J003 | |
| Person / Time | |
|---|---|
| Site: | Fort Saint Vrain  |
| Issue date: | 09/16/1981 |
| From: | Lee O PUBLIC SERVICE CO. OF COLORADO |
| To: | Eisenhut D Office of Nuclear Reactor Regulation |
| References | |
| RTR-NUREG-0612, RTR-NUREG-612, TASK-A-36, TASK-OR P-81228, NUDOCS 8109290491 | |
| Download: ML20010J003 (4) | |
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s PUBLIC SERVICE COMPANY OF COLORADO P.
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Unit No.1 ID P-81228 64 g g$Ns%;*e
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Mr. Darrel G. Eisenhut, Director v
Division of Reactor Licensing Office of Nuclear Reactor Regulation U.S. Nuclear Regula*ory Commission Washington, D.C.
20555
Subject:
Reference:
Letter December 22, 1980 Gentlemen:
The following is Public Service Company of Co!orado's six month response to the criteria of NUREG-0612 on the handling of heavy loads.
PSC's response is based on the fact that Fort St. Vrain is a High Temperture Gas-Cooled Reactor (HTGR) rather than a water reactor, and therefore we are submitting answers with this difference in mind.
ITEM 1,, Request for Additional Information on Control of Heavy Loads.
2.1 General Requirements for Overhead Handling Systems 1)
The results of the revicw of the plant arrangement has identified two handling systems from which a load drop may result in damage to a system required for plant shutdown.
The two handling systems are the reactor building crane and the turbine building crane.
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P-81228 Page 2 September IE,1981 2)
The crane in the turbine building can be excluded from the list of potentially hazardous cranes with respect to load drops since it does not have the requirement nor the capability to carry a heavy load as defined in NUREG-0612.
(
Loads such as parts from a turbine overhaul that have censiderable weight, but not classified as a heavy load would rot be carried by the turbine building crane when the plant was operating.
3) a.
During plant operation no loads are carried over the Prestressed Concrete Reactor Vessel (PCRV). This is the only area restricted from travel by the reactor building crane during plant operation. The restricted crane area, as well as the spent fuel storage and safety-related equipment are shown on the attached sketch.
It should be noted that for Fort St. Vrain, other than the area over the PCRV, there is no need to define safe load paths for the travel of the reactor building crane. The reason for this as cxplained in the FSAR, Section 9.2.1, is primarily because the design of the load handling system makes it virtually impossible to have a taavy load drop.
b.
Personnel operating the reactor building crane are required by written approved procedures not to allow any movement af the crane over the PCRV at any time, except during refueling. The crane operators are
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required to follow PSC's Crane Operating Procedure
(
Manual in which these procedures of crane operation are spelled out. These procedures are reviewed each refueling with the Fuel Handling People.
Administrative controls, as defined in the Technical Specifications, Section 7.4.2, would be followed to deviate from these procedures, c.
As defined in the NUREG-0612, PSC has only one heavy load that is handled by the reactor building crane.
The total weight of the heavy load is 165.5 tons.
This is the weight of the fuel handling machine plus the weight of a fuel element. The designated lifting device is the reactor building crane. The operation of the crane when engaging the fuel handling machine is governed by PSC's Fuel Handling Procedure and by PSC's Crane Operating Procedure.
These procedures contain the information rettired in NUREG-0612, section 5.1.1(2).
P-81228 Page 3 September 16, 1981 d.
All lifting devices comply with the requirements of ANSI B30.9-1971.
These requirements are contained in PSC's Crane Operating Inspection and Maintenance Procedure.
e.
ANSI B30.2-1976 has been invoked with respect to crane inspection, testing, and maintenance. These requirements are contained in PSC's Crane Operating Inspection and Maintenance Procedure.
All reactor crane operators at Fort St. Vrain are required to follow these procedures.
No exceptions are taken to this standard.
f.
The crane was originally specified and designed in 1967, to E0CI Spec. #61.
In 1972 the crane was reanalyzed and upgraded to conform to CMAA 70 specifications, g.
There are no exceptions taken to ANSI B30.2-1976 with respect to operator training, qualification, and conduct.
ITEM 2, Confirmation of Imple:nentation and Modifications of Changes Found Necessary.
PSC has no plans for any modifications to the ove-head handling systems at this time.
If upon further research in response to sections 2.2, 2.3 and 2.4 of enclosure 3, modifications are found necessary, they will be started as soon as possible and completed within two years of our submittal of section 2.4 of enclosure 3.
ITEM 3, Modifications to enclosure 1 which are felt to be not j
necessary.
At this time, no changes to enclosure 1 are proposed.
4 However, it must be kept in mind that Fort St. Vrain is not a water type reactor and modifications to cranes that may be required at some plants (such as handling of fuel around fuel storage pools) do not apply at Fort St. Vrain.
Respectfully,
'h 0.R. Lee, Vice President Electric Production ORL/ RAG:pa
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