ML20023C166
| ML20023C166 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear |
| Issue date: | 04/27/1983 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20023C167 | List: |
| References | |
| NUDOCS 8305110626 | |
| Download: ML20023C166 (2) | |
Text
.-
1 e
- will have a module configuration with dimensions of four 9 x 9, two 8 x 9, four 9 x 10 and two 8 x 10 feet. These modules will weigh from 13,000 lbs. to 20,300 lbs. The above configuration i
maintains cell pitch of 10.65 inches at ANO-1 and 9.8 inches at ANO-2 and prevents placement of a fuel assembly anywhere other than a design location.
The proposed neutron absorber fuel racks are designed to seismic Category I criteria. Structural and seismic analyses have been performed by, the licensee to verify that the rack design is adequate to withstand 3
normal operating, seismic and accident loading conditions.
Rack Handling and installation The review of heavy load handling at ANO-1 & 2 is being conducted as part of the ongoing generic review initiated by NUREG-0612 " Control r
i of Heavy Loads at Nuclear Power Plants." The results of tnat review will
.be reported as part of Multiplant Action Item C-10.
The evaluation provided herein is limited to the heavy load handling activities associated with the proposed spent fuel storage modifications.
Each unit has one seismic Category I overhead crane in the auxiliary building which will be used for removing the existing rack modules and lowering the new modules into the pool. The licensee has stated in its November 5,1982 submittal that "no loads exceeding 2000 lbs. will be allowed i
over the fuel assemblies at any time." The TSs for ANO-1 & 2 also prohibit the travel over fuel assemblies in the storage pool of loads in excess of 2000 lbs. Since the weight of a rack module is much greater than 2000'1bs.,
l we conclude that the rack modules will not be carried over the fuel assemblies and that there is reasonable assurance that an accident impacting
)
assemblies in the pool will not occur. All movement of spent fuel racks will be controlled by written administrative procedures which will prohibit
{
movement of the racks over locations 'in the pool where fuel is stored.
1 The licensee has committed to establish a program for installation and use of slings which complies with the criteria contained in ANSI 330.9-1971.
I In NUREG-0612, we concluded that this is acceptable.
The licensee also stated in response to NUREG-0612 that all crane operators and signalmen will be trained in accordance with ANSI-830.2-1976, and no exceptions from the standards are taken regarding training, qualification or operator conduct.
l i
3305110626 830427 Mt ADOCK 05000313 l
The licensee does not expect'any significant increase in dose rates due to the buildup of crud along the sides of the pools.
If crud buildup everitually l
becomes a major contributor to pool dose rates, measures will be taken to reduce i
such dose rates. The purification system for the pools includes filters and demineralizers to remove crud and will be operating during the modifications of the pools.
The licensee has presented four alternative plans for removal and disposal l
of the old racks. These are (1,2) burial with or without volume reduction; (3) decontaminate to releasable criteria of Regulatory Guide 1.86 and disposal; (4) to have an outside vendor chemically decontaminate and dispose of the intact racks. The disposal methodology will follow ALARA 3
guidelines for each of the alternatives.
The licensee has an ALARA committee, which reviews all work in radiological 4
controlled areas when the estimated collective dose for any job will exceed I man-rem. Some of the actions that will be taken by the licensee to assure that occupational doses during each task of the pool modifications will be ALARA are:
P 1.
A health physicist and diving supervisor will be in direct communication with the divers at all times during the re-racking to monitor for excessive exposure by utilizing portable or hand-held radiation monitoring instruments. The doses will not be pennitted to exceed 1 rem whole body.
2.
Personnel monitoring devices will be used by all personnel working in the radiologically-controlled area. Additional monitoring of the underwater divers will be done by multiple whole body TLDs and i
extremity TLDs.
3.
Personnel shall be required to wear appropriate protective clothing as detennined by the health physicist to preclude contamination.
4.
As the racks are pulled out of the water, they will be washed.
5.
Area radiation monitors will be used to alann on a high radiation signal. Actual dose rates can be read locally and in the control room.
6.
A portable filtered water vacuum system will be available to remove loosely deposited contamination from the fuel rack surfaces, i
pool floor and walls near' divers' working areas to reduce the radiation exposure.
7.
Contamination control measures will be used to prevent the spread of contamination and to protect personnel from internal exposure from radioactive material.
f r
e 9
- 9
'4y w
w,
,e w.
y