ML20031G811

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Revised Pages 30,30A,50 & 50A to 810427 Application for Amend 3 to License SNM-1882 to Permit Neutron Detectors to Be Transported to Turbine Bldg
ML20031G811
Person / Time
Site: 07002936
Issue date: 10/09/1981
From:
MISSISSIPPI POWER & LIGHT CO.
To:
Shared Package
ML20031G808 List:
References
19795, NUDOCS 8110260045
Download: ML20031G811 (4)
v • d • e


Text

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SNM License April 15, 1981 Amendment 3 Page 30 Special Nuclear Material (In-core Detectors)

Quantity Description Grsms U-235 Activity (microcuries)

(See Note Per Per Below Detector Total Detector Total

-6

-5 12 SRM Detectors

.0027

.0324 5.85 x 10 7.02 x 10

-6

-5 16 IRM Detectors

.00074

.01184 1.62 x 10 2.592 x 10 352 LPR1 Detectors.00022

.07744 5.1 x 10 1.7952

-6

-5 10 TIP Detectors

.000744

.00744 1.62 x 10 1.62 x 10 NOTE: All of the above devices are sealed sources.

Neutron detectors may be temporarily stored in the MP&L warehouse under the auspices of the Interim Security Plan.

The neutron detectors will be stored in a locked area whilt in the warehelse.

[SEE ATTACHED PAGE 30A]

The TIP detectors will be stored 'nside the vessel in the TIP guide tubes or in the TIP storage tubes located between the weir wall and drywell wall.

The areas containing these detectors will be designated and posted as radiation areas if required.

The Radiation Protection Manager has overall responsibility for radiation protection (see Figures 11 and 12).

Radioactive Sources Description Quantity Isotope Est. Activity Each Operational 14 Sb124 1400 Curies Source (Seven (7) operational sources with two (2) 1400 Curie pins each)

The opert ional sources will be shipped in lead filled drums approximately 48" tall and 31" in diameter, which meet DOT package specifications (Figure 13). The source is positioned within a 7" diameter x 25" long cavity which is centered in the drum and surrounded by lead shielding.

The cavity is sealed with a lead plug.

This shipping container is a General Electric Model 1500 Shielded Container, licensed with the DOT under S.P. No. 5939.

Consistent with recommendations of Regulatory Guide 8.8, MP&L has committed to establish a health physics program to maintain occupational and geaeral public exposure to radiation "As Low As Reasonably Achievable" (ALARA). The ALARA program is contained in Administrative Procedure No. 01-S-08-2.

1 e m o t-M 4 JV) 0110260045 011009 PDR ADOCK 07002936 C

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SNM License October 5, 1981 Page 30A INSERT A 3

The nentron detectors (SRM, IRM, LPRM detectors) will be transported from the warehouse to the temporary detector inspection and assembly room located on Elevation 166' of the Turbine Building (see Figure 16).

Here the detectors will be unpacked, inspected, and assembled into their l

respective dry tubes. The assembled dry tubes will then be packaged for movement to the Auxiliary Building into the Containment Fuel Handling Area.

The detector inspection and assembly room is a completely enclosed L

structure. This room is constructed at this location to preclude j

interference from surrounding construction activities.

When the area is unoccupied, it will be locked, and the lock and key will be controlled by security. The inspection and assembly area will be checked by a periodic security patrol. Fire extinguishers and smoke detection will be provided at the inspection and assembly room for fire protection.

Radiation protection personnel under the direction of the Radiation Protection Manager shall be responsible to implement, in accordance with written plant procedures, any required radiatian protection measures such as posting of radioactive material areas, performing contamination surveys, or providing personnel dosimetry.

Following the assembly of the detectors in their respective dry tubes, they will be packaged an1 may be temporarily stored in the inspection a

and assembly room. The detectors will then be moved from the Turbine Building to the Auxiliary Building at Elevation 166' (see Figure 17) and into the Containment through the construction equipment hatch also at Elevation 166'.

The packaged detectors will then be hoisted to the Containment Fuel llandling Area at Elevation 208'-10".

The detectors will reside here until they are unpacked and installed in'their normal use configurations in the reactor vessel.

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