ML19249A501
| ML19249A501 | |
| Person / Time | |
|---|---|
| Site: | Zimmer, 07002838 |
| Issue date: | 04/12/1979 |
| From: | Flynn J CINCINNATI GAS & ELECTRIC CO. |
| To: | Crow W NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| Shared Package | |
| ML19249A479 | List: |
| References | |
| NUDOCS 7908230164 | |
| Download: ML19249A501 (5) | |
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u TIIE CINCINNATI GAS & ELECTitIC COM i*ANY CMC'" % " 4W'i CINCity N ATI O HIU 4 5201
/pril 12, 1979 Reference No. 070-02838
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U.S. Nuclear Regulatory Commission Uranium Fuel Fabrication Section Division of Tucl Cycle and Material Safety E- - @MibiU RUEN Washington, D.C.
20555 Attention:
Mr. William T. Crow, Section Leader RE:
WM. H.
ZIMMER NGCLEAR POWER STATION-UNIT J.
REVISION OF LICENSE APPLICATION FOR STORAGE ONLY OF UNIRRADIATED REACTOR FUEL AND ASSOCIATED RADIOACTIVE MATERIAL - LICENSE NO. SNM-1823 Gentlemen:
Enclosed are eight (8) copics of revised pages to our license application for storage only of unirradiated reactor fuel and associated radioactive material at the En. H.
Zimmer Nuclear Power Station-Unit 1.
These revisions (underlined in red) are with regard to three (3) fuel handling crancs to be utilized for receiving and storage of fuel assemblies as outlined in Section 7.
Please amend the subject licence to incorporate these revisions and insert the replacement pages into the eight (8) copics of the license application transmitted to you with our letter of March it, 1978.
Very truly yours, TIIE CINCINNATI GAS & ELECTRIC COMPANY
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BY J1LME D.
FLYNN, Manager Licensing and Environmental Affairs DEF:gaj Enclosures cc:
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- 7.
STORAGE CONDITIONS (Co n t ' d )
7.2 Receiving (Cont'd)
M4, Sheet 1 and 2).
IIere the shipment is initially inspected, the inventory chechcd against the receiving documents and receipt of clearance for unloading obtained. Each container is unloaded frcm the truck trailer using a fork lift truck, cherry _p.ickerf or crane sling in -
combination with the overhead crane pr_the 4 ton nqs fuel handling _jiberane.
The outer shipping containers will be removed and the fuel bundles, still within their metal containers, will be lifted using the reactor building crano to the refueling ficor for removal from their containers, inspection, channeling and final storage prior to fuel loading.
Elevations and plan views of tne reactor building showing the fuel storage areas are shown on Figure M-8.
7.3 Storace As described in Section 7.2, the metal fuel containers are lifted to the refueling floor, elevation 627' 9" of the reactor building utilizing the reactor building crane auxiliary hook.
Temporary storage space for the fuel containers is provided on the north and west portions of the refueling floor.
From the temporary storage location, each metal container is positioned horizontally on the operating (re f ueling)
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7.
STORAGE CONDITIO::S (Cont'd) 7.3 Storage (Cont'd) floor, the cover removed, the contents visually inspected to verify that no damage during shipping has occurred, and radiation control measures as described in Section 11 are implemented.
After installation of special fuel bundle holddown bars and removal of the end cover, the container is pivoted to the vertical position and secured to a vertical support adjacent to the fue.' inspection stand.
Each fuel bundle is removed in turn from the con-tainer and is transferred to the new fuel inspection stand.
The fuel inspection station is a " clean" area where the assemblies are checked for damage, cleanliness, and specified clearances.
Following inspection, the fuel assemblies are channeled and placed in the spent fuel storage racks, located in the spent fuel storage pool, Figure M-8.
Movements of fuel containers on the reactor building 627' 9" elevation are accomnlished using the auxiliary hook of the reactor building crane and/or a wheel mounted crane (ch_crry_eicker) temp.orarily_p_ laced on the 627' 9"
elevation.
Fuel assemblies will be moved using the reactor building crane auxiliary hook, the refueling platform fuel grapple, _the 1,000 lb. fuel handling _ jib-
_ crane _or_the_ temporary _. wheel mounted crane.
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STORAGE CONDITIONS (Con t ' d )
7.3 Storage (Cont'd) mounted crane consists of a rotating _ superstructure with telescoping boom, mounted on a platform _ equipped, with rubber-tired wheels, storace outriggers and a prop _ane fueled diesel engine.
The cranc shall be Icad tested to at least 2200 lbs. which is approximately_
110% of a loaded metal shipping _ containers weight of 1900 lbs., and 320% of a fuel bundles weight of 685 lbs.
During the load test, th_e boom sh_all be extended to 4
its maximum permit.ted_ limit _and lowered to its rf nimum permitted elevation angle.
Further discussion on the receipt and handling of new fuel is also provided in FSAR Section 9.1.4.3.1.
Drawings of the temporary new fuel storage area an.1 the spent fuel storage
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STORAGE CO:1DITIO:JS (Cont'd) 7.5 New Puel llandline Cranen The approximate weight of a new c x 8 fuel assembly is 685 pounds.
The cranes listed below, and further described in FSAR Section 9.1.4, will be used for handling the new assemblics.
7.5.1 The reactor building overhead crane with a 110 ton ma.in hoist cnd a 10 ton auxiliary hoist.
7.5.2 The refueling platform with a 1200 pound fuel grapple.
7.5.3 The 1000 pound jib crane.
7.5.4 The _4_ ton new fuel handling jib crane.
7.5.5 The temporary _ wheel mounted crane (cherry _ picker).
7.6 Fire Protection The temporary new fuel storage area and the spent fuel pool are located on the reactor building refueling floor, elevation 627' 9".
The details for the fire protection systems provided are presented in the " Fire Protection Evaluation neport" for Unit 1, issued February 4, 1977.
The refueling floor consists of structural concrete and the walls and roof are constructed of steel framing with corrugated metal siding.
There are no combnstibles normally located in the area, thus the fire loading is negligible.
Any possible fire in the area would involve transient materials possibly present during fuel transfer.
No accumulation of flammable material is permitted.
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