ML20053C894
| ML20053C894 | |
| Person / Time | |
|---|---|
| Site: | 070*****, 07002961 |
| Issue date: | 05/13/1982 |
| From: | UNION ELECTRIC CO. |
| To: | |
| Shared Package | |
| ML20053C890 | List: |
| References | |
| 20704, 22130, NUDOCS 8206030129 | |
| Download: ML20053C894 (6) | |
Text
-
SNMLA 6
structure so that there is a clearance between the fuel rod ends and the top and bottom nozzles.
The fuel assembly structure consists of a bottom nozzle, top nozzle, guide thimbles, and grids.
The bottom nozzle serves as the bottom structural element of the fuel assembly and is fabricated from Type 304 stainless steel.
The top nozzle assembly functions as the upper structural element of the fuel assembly and is made of Type 304 stainless steel.
The top nozzle springs and bolts are made of Inconel-718.
The guide thinbles are fabricated from Zircaloy-4 tubing having two different diameters.
The larger diameter is at the top and the smaller at the bottom.
The guide thimbles are joined to the grids and the top and bottom nozzles to create an integrated structure.
The fuel rods are supported at intervals along their length by grid assemblies which maintain the lateral spacing between the rods.
Each fuel rod is supported within each grid by the combination of support dimples and springs.
The grid material is Inconel-718.
The length of a fuel assembly is opproximately 160 inches.
The fuel rods consist of uranium dioxide ceramic pellets contained in slightly cold worked Zircaloy-4 tubing which is plugged and seal welded at the ends to encapsulate the fuel.
The fuel pellets are right circular cylinders consisting of slightly enriched uranium dioxide powder which has been compacted by cold pressing and then sintered to the required density.
The ends of each pellet are dished slightly to allow greater axial expansion at the center of the pellets.
l The fuel assemblies are fabricated by Westinghouse Electric l
Corporation.
A more detailed description of the fuel assemblies to be stored is set forth in the Standardized Nuclear Unit Power Plant System (SNUPPS) FSAR, Section 4.2.
1.1.3 URANIUM ENRICHMENT The fuel assemblies are grouped into three regions, each region having a different nominal enrichment:
Region 1 contains a nominal 2.10 w/o U-235, Region 2 contains a nominal 2.60 w/o U-235, Region 3 contains a nominal 3.10 w/o U-235.
The average core enrichment is approximately 2.60 w/o U-235.
A nominal enrichment is the design enrichment plus or minus a manufacturing tolerance.
The maximum enrichment under this license will be 3. 5 w/o U-235.
Each fuel assembly will contain approximately 461 kg of uranium an uranium dioxide.
1.1.4 Number of Fuel Assemblies and Weight of U-235 The maximum quantity of special nuclear material for Callaway Unit 1 including one initial core of 193 fuel hhRkhofk9820513 Rev. 1 9 O*****
5/82 C
PDR J
SNMLA assemblies and allowance for extra material onsite will be 2,400 kg of U-235.
S 6
9 8
- 3a -
Rev. 1 5/82
~
SNMLA I
The new fuel assembly handling tool is a short-handled device located on the cask handling crane monorail.
The new fuel. assembly handling tool is used to handle new fuel on the operating deck of the Fuel Building, to remove the new fuel from the shipping container, and to facilitate -
inspection and storage of the new fuel and loading of fuel into the new fuel storage racks or the new fuel elevator.
The new fuel assembly handling fixture employs four cam-i actuated latching fingers which grip the underside of the fuel assembly top nozzle.
When the fingers are latched, the safety mechanism on the side of the tool is turned in to prevent accidental unlatching of the fingers.
The new fuel t
elevator (Figure 1.2-6) consists of a box-shaped assembly with its top end open.
The elevator is sized to house only one fuel assembly.
The elevator is. located on the wall of the cask loading pool and is used exclusively to lower a new fuel assembly to the pool bottom.
The spent fuel bridge crane (Figurc 1.2-7) is a CMAA No.-70, Class B type and is designed to maintain its integrity during a Safe Shutdown Earthquake (SSE).
The crane consists of.a 5-ton-capacity wheeled bridge structure with steel deck walkway, a 2-ton motorized monorail trolley, and a 5-ton manual push-type trolley.
The crane has interlocking capabilities with the new fuel elevator.
The 2-ton electric hoist of the crane will be used for transfer of the new fuel assemblies from the new fuel elevator to storage in the spent fuel pool.
Control will be from a pendant station supported from the trolley.
The spent fuel ~ assembly handling tool (Figure 1.2-8) will be used to manually handle the new fuel in the spent fuel pool.
An' operator on the spent fuel bridge guides and. operates the tool.
The tool is designed to maintain its integrity during an SSE.
The tool employs four cam-actuated latching fingers which grip the underside of the fuel assembly top nozzle.
When the fingers are latche'd, a lock pin is inserted into the operating handle to prevent the fingers from being accidentally unlatched during fuel handling operations.
1.2.4 Fire Protection i
Fire protection for the railroad bay and the new fuel shipping container storage and unloading area is provided by a proaction sprinkler alarm system which can be triggered by j
l a local pulldown station.
Additional fire protection is l
provided by two permanently mounted fire hose racks (75 l
feet), two 2 1/2 gallon water extinguishers, two 20-pound i
I carbon dioxide extinguishers, and one 30-pound dry chemical r
l
. extinguisher.
Fire protection for the new fuel storage area consists of one 20-pound carbon dioxide extinguisher and one 2 1/2-gallon water extinguisher.
There is also one permanently I Rev. 1 5/82
SNMLA The possibility of a criticality accident is considered remote due to the design of the fuel handling and storage equipment and the administrative: controls.
The possibility of fuel damage due to fire in the fuel storage area is considered remote due to the limited supply of combustible mat'erials and administrative controls governing ignition sources.
3.0 OTHER MATERIALS REQUIRING NRC LICENSE'
.l 3.1 Other Special Nuclear Materials Other special nuclear materials for which a license is requested consists of:
l 3.1.1 Uranium-235 in the following form and quantity.
Form:
Approximately 93% U-235 l
Amount:
78.0 mg Uranium Oxide (U308) l (61.5 mg U-235)
Capsulo Type:
Fission chambers manufactured by Westinghouse Electric Corporation -
Industrial and Government Tube Division, Model Number WL-23630 (15 chambers)
Amount / Chamber:
5.2 mg nominal Uranium Oxide (U308)
(4.1 mg nominal U-235)
The fission chambers will'be used in the.Incore Detector system for Callaway Unit 1.
Prior to use the detectors will l
be stored in the Moveable Incore Detector Vault located on I
the operating. floor of the Fuel Building.
l 3.1.2 Uranium-235 in the following_ form and quantity.
I Form:
Uranium enriched 93% in U-235 Amount:
3.2 gms U-235 Uranium Oxide (U308 or UO2 l
at supplier's discretion)
Capsule Type:
Fission counter manufactured by Reuter Stokes, Model Number RS-P6-1608-110 (2-counters) l Amount / Capsule:
1.6 gms U-235 Uranium Oxide (U308 or UO2 I
at supplier's discretion)
The fission counters will-be used in the Post Accident Sampling System.
Prior to use the counters will be stored in the Moveable Incore Detector Vault located on the operating floor of the Fuel Building.
l Rev. I w --
_ _ _ _ _ _ _ _ _ _ _ _ __5/82
SNMLA O
l 3.2 Storage Information The onsite storage of radioactive material will comply with or exceed the requirements of 10CFR20.
1.
Source storage areas will consist of a barrier wall or fence and lockable door.
The storage area will be constructed such that radiation levels will not exceed the range of a radiation area (10CFR20.202(b)(2)) on the outside confines of the barrier as a result of stored radioactive material.
2.
The area will be posted in accordance with 10CFR20.203.
3.
Containers and storage casks containing radioactive material will be labeled pursuant to 10CFR20.203(f).
s
- 12a -
pey, 1 5/82
SNMLA O
4.
Access to radioactive material storage areas will be controlled by the Health Physics group.
The storage area will be locked when unattended.
5.
Radioactive material storage areas will be surveyed permudically for radiation and contamination.
6.
Radioactive material stored in uncontrolled areas will meet the requirement of 10CFR20.105 in addition to the requirements listed above.
l The fission chambers and fission counters will not be used I
for any purposes other than storage until installation.
3.3 RADIATION PROTECTION The storage and use of the radioactive materials identified in Section 3.1 will be conducted under the scope of the Health Physics program as described in Section 12 of the Callaway Plant FSAR.
In addition, the equipment, facilities and radiological safety provisions described in the byproduct license application dated October 6, 1980, as refereaced by the Callaway Pl ant broad scope byproduct license number 24-02020-06, tre applicable to activities involving these radioactive sources.
Health Physics coverage will be provided during the use or transfer of the described ladioactive sources.
. Rev. 1 5/82 c-.
_ _ _ _ _