ML20039A157
| ML20039A157 | |
| Person / Time | |
|---|---|
| Site: | Grand Gulf, 07002936  |
| Issue date: | 11/25/1981 |
| From: | MISSISSIPPI POWER & LIGHT CO. |
| To: | |
| Shared Package | |
| ML20039A149 | List: |
| References | |
| NUDOCS 8112160283 | |
| Download: ML20039A157 (7) | |
Text
7 T*
SNM License November 25,1981 Amendment 3 Page 32 S.
The shipping container will then be transferred through the equipment hatch to Elevation 166'-0" and into the Containment Building.
o 6.
The shipping container is then lifted to Elevation 208'-10".
7.
The jacket is then lifted off the lead cask and Health Physics will survey the lead cask.
8.
The shielding cask lid bolts are removed, the lid will remain in place.
9.
T'.e lead cask containing the Sb sources is then lowered into the upper containment pool and brought to rest on the bottom of the pool at Elevation 184'-6".
The pool will be filled with water.
When pool level is established at Elevation 207'-10", the cask lid may be reicoved. The individual sources will then be loaded into the seven source holders (see Figure 14). The estimated dose for this procedure is less than five millirem per hour. When all source holders are loaded and in place in the source holder rack, the source holder rack will be transferred to the reactor cavity. The top of the source holder rack will be submerged at least five feet at all times during transfer operations. The source holders may then be installed in their designated positions inside the reactor vessel. The source holders will remain submerged at least five feet at all times during installation. The estimated exposure rate for installation of the seven source holders is expected to be less than 20 millirem per hour.
Dose rates are estimated to be 30-60 millirem per hour at the surface of the cask and 2-3 millirem per hour at 3 feet from the cask (in air). To minimize exposure, access to the Containment Building will be restricted during source handling, transfer, and installation to those personnel directly involved with source handling operations or radiation monitoring. Radiation protection personnel will be continuously present during all source handling operations.
Radiation prot'ection personnel will be responsible for operating standard radiation survey instrumentation including a portable tissue equivalent neutron detector. TLD's and self-reading dosimeters will be provided to all personnel to monitor personal exposure. Radiation surveys will be conducted of the area after the transfer has taken place. Consistent with MP&L's ALARA policy, a minimum of 5 feet of water will be maintained above the sources when moving them to provide proper shielding. Also, a minimum of 5 feet of water shielding will also be provided above the lead cask containing the sources upon removal of the cask lid.
It will be MP&L's ALARA goal to limit the maximum exposure to any individual involved in source handling operations to less than 30 millirem (whole body), and to limit exposure to all individuals involved in source handling to less than 0.2 man rem.
[SEE ATTACHED PAGE 32A]
8112160283 811200 PDR ADOCK 05000416 A
f
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SNM License Novoober 25, 1981 Page 32A INSERT A Description Quantity Estimated Activity Shielded Waste Container 91.36 Kg U-238 (depleted) 32.8896 mci e
f The shielded waste container (Figure 18) consisting of a Icad cask with a plug (Figure 19) containing depleted U-238 and an aluminum catch bucket, is designed to cut and store by remote control, in conjunction with related disposal equipment, the irradiated portions of LPRM detector assemblies upon their removal from the teactor. -Only the plug portion of the container assembly contains U-238 (depleted). The container may be stored temporarily in the MP&L warehouse. While stored in the warehouse the container will be maintained in a locked area.
In conjunction with preoperational testing of the disposal apparatus, the container may also be located in the following areas:
a)
Elevation 100'-9", inside the drywell (Figure 20).
I b)
Elevation 105'-2" and Elevation 117'-4", inside the drywell and Elevation 117'-4" inside the containment. This includes the area under the vessel at Elevation 117'-4" (Figure 21).
c)
Elevation 166'-0", CRD Repair Room (Figure 22).
The shielded waste container and attendant disposal apparatus will at no time prior to receipt of an operating license be used for disposal of irradiated material. Further, no testing of this system will be conducted with irradiated material.
The approximate weight of the assembled cask and the cart used to transport the cask is 5410 pounds.
i
SNM License h
November 25, 1981 i
Page 51A
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