ML20039B699
| ML20039B699 | |
| Person / Time | |
|---|---|
| Site: | Fort Saint Vrain  |
| Issue date: | 12/14/1981 |
| From: | Lee O PUBLIC SERVICE CO. OF COLORADO |
| To: | Eisenhut D Office of Nuclear Reactor Regulation |
| References | |
| REF-GTECI-A-36, REF-GTECI-SF, RTR-NUREG-0612, RTR-NUREG-612, TASK-A-36, TASK-OR P-81316, NUDOCS 8112230439 | |
| Download: ML20039B699 (3) | |
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PUBLIC SERVICE COMPANY OF COLORADO P.
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- DENVER, COLORADO 80200 Fort St. Vra'in OSCAR H. LEE vcc e.,oc~,
Unit No. 1 P-81316 Mr. Darrel G. Eisenhut, Director Division of Reactor Licensing Office of Nuclear Reactor-Regulation p _L.1f4 U. S. Nuclear Regulatory Commission Washington, D. C.
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Docket No. 50-267 t
DEC 2 21981> u a
Subject:
Control of Heavy Lc
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Reference:
Letter dtd 12/22/80
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s Gentlemen:
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The following is Public Service Company of Colorado's nine month response to the criteria of NUREG-0612 on handling of heavy loads.
PSC's response is based on the fact that Fort St. Vrain is a High Temperature Cas-Cooled Reactor (HTGR) rather than a water reactor, and therefore our response is applicable to the HTGR concept. of NRC letter dated December 22, 1980 requested additional infonnation on control of heavy loads.
SECTION 2.2 Specific requirements for overhead handling systems operating in the vicinity of fuel storage pools.
PSC RESPONSE:
Fort St.
Vrain (FSV) is a HTGR and does not use a fuel storage pool.
Spent fuel -is contained in steel vessels which are stored in concrete vaults below the refueling floor, the location of which can be seen in the sketch attached to our September 16, 1981 letter on Control of Heavy Loads.
' Since FSV has no fuel storage pools that could be affected by a load drop, no response to this section is requi red.
SECTION 2.3 Special Requirements of Overhead Handling Systems Operating in the Containment.
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P-81316:
. Page-2 December 14, 1981-
~PSC RESPONSE 1)
The design :of Fort St. Vrain,is._such that the ' term
- containment is taken to mean: reactor. building.
The crane bsed in 'this area is the reactor building ; crane as discussed in SECTION 2.1 of.our September 16, 1981 response to Control
. of Heavy Loads.
This crane is 'an overhead ' traveling type-crane, the capacity is l'.0 tons and _ designated by equipment number. G7201.
2)
The reactor building crane' is - the only. crane _ capable of
. carrying a heavy load -ove.r the reactor vessel, therefore no-other cranes need be included in.this category.
3)
- The reactor. building crane has sufficient design features so 1
that the. probability of a. load drop is. extremely small.
A snubber system. on the crane.is so_desig'ned that in no case will the fuel handling machine (165.5 tons) come in contact' with the refueling floor except at-isolation valve locations which are designed to receive 'the fuel handling' machine. An
-indicating light is provided on the crane control station to indicate that the snubber system.is positivelyj engaged for opera ting.. The snubber ' system is designed to support the-165:5 ton fuel-handling. machine plus; impact in the case ofz cable breakage and -limit' the vertical travel of the hoist system to 14' inches.. This device is:in.uddition -to.two DC-magnetically operated shoe-type brakes _.plus an eddy current braking system.
See-Attachment'1.to this-letter. for. the -
additionally requested. reactor building crane i_n_ formation.
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No' further response to this section is required.
SECTION 2.4 Special requirements for overhead handling systems operating in plant areas containing equipment-required,for reactor shutdown, core decay, head removal, or spent fuel pool ' cooling.
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~ PSC RESPONSE There are no cranes operating in plant areas where the specified L
systems are located.
Also as stated in Section 2.2, Fort St. Vrain
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is.an HTGR and does not have a spent fuel pool.
The systems required i
for reactor shutdown 'and ' core-heat removal are not contained in..the
. same - ~ area as the reactor building crane, which is the only overhead; crane with the capability of carrying-a heavy load.
Therefore, the' reactor. building crane does not need to be further analyzed per -
SECTION 2.4.
d Very truly yours, Jf NePresident 0.R.
ee, Electric Production ORL/ RAG:pa Attachment w-g m
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' ATTACHMENT 1 FORT ST. VRAIN REACTOR BUILDING CRANE SINGLE-FAILURE-PR0OF'HA? IDLING SYSTEMS
'1)
The manufacture of the reactor building crane is Whiting Corporation.
The design-rated load (DRL),is 200 tons.
The maximum critical load is 170 tons.
2)
The crane was designed by. Whiting Corporation in.accordance with EOCI Specification #61. and reanalyzed and certified - to Cl1AA-70 in 1972.
The crane is inspected, tested, and operated in. accordance with PSC's.
crane operating, inspection, and maintenance procedure.
PSC meets.the requi rments contained in CMAA-70 and therefore is in compliance with the intent of'NUREG-0554.
- 3)
The reactor._ building crane has been designed to retain its
-load'during-a SSE Seismic Eveat.
This is shown by the following simple analysis.
The design rated load for the
. reactor. building crane is 200 tons and' the maxinun' vertical' seismic acceleration for Fort St.
Vrain is 0.15g. The maximum seismic plus dead weight load on the crane would :be 190 tons '(1.15' x 165.5 = 190 tons). The exact method of
- analysis. &, assumption.made..in-the mathematicalymodel is not known L since, the. detailed calculations were made by Whiting Corporation,'and:this inforation is not available to PSC.-
4&S) No infomation is~ available on the design and analysis details of the' interfacing lift points and - special lifting devices. As stated:in.section 3,.the crane was analyzed and designed by Whiting l Corporation to meet the applicable specification (E0CI-61)~ at timetof purchase and:at a later-date the crane was reanalyzed by Whiting to meet CMAA-70.
PSC considers the crane to-be adequate and sufficient to carry heavy loads at Fo'rt-St. Vrain and to be in conformance-with NUREG-0612.
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