ML19319D425
| ML19319D425 | |
| Person / Time | |
|---|---|
| Site: | Crystal River  |
| Issue date: | 05/31/1973 |
| From: | Kastner J US ATOMIC ENERGY COMMISSION (AEC) |
| To: | Buckley B US ATOMIC ENERGY COMMISSION (AEC) |
| References | |
| NUDOCS 8003170559 | |
| Download: ML19319D425 (2) | |
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B. Buckley, Project Manager, Pressurized Water. Reactors Branch No. 4r.
INFORMAL. DISCUSSION QUESTI0ils FOR RA3 SITE VISIT TO CRYSTAL RIVER U'IIT 3
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The following items should be discussed irith the appropriate # personnel.
from Florida Power Compay or their consultants or subcontractors at -
' the site visit to Crystal River Unit 3 tantatively scheduled for late
.t June. - It is not required:that the' material specified be provided in
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a formal-submission,. since the plant construction is already far along, and since the sufficiency.of.the in plant shielding will be tested in the start up testing program.. The RA3 participant in the forthcoming.
Discussion Items:
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discussions will probably be Joseph Craf.
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.g 11.3.1 Provide the maximum Erie' amounts of radioactivity excected in equipment listed in TSAR Table 11-13, and shown in Figures 11-1 and 11-2 for which shield walls are snacified.
Curie amounts should be specified by principal nuclides.
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- 11. ';,2 For cc nrincipal sources of radicactivity and radiation in the plet, as identified in Table 11-13 and Figures 11-1 and 11-2 of the FSAR, describe the rethods by which the
- shield thickness was datermined, including all pertinent 4
assumptions used in the calculaticns. Describe the calculational method, ne simplifying assumptions mde, if any, the characterintion of source..(line, point,
- i-e volum, etc.) and desi;n. bases.
111.3.3, Provide estimates of the amount of time that will. be spent f fYby the plant personnel in the areas for which dose-rate
? Wff$1evels ~are specifled:on. page 11-11,:as well as the. time espont:on' maintenance' activities < in compartments containing -
1/CW"Mipment that'.will'be. contaminated.DUsing these
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3rovids0the--satinated Wearly
- PA$$[FpersonnelhThiFdetamination/ dose expec ishould include dose received' n_A frosi inhalation 71 f. any,Tof liitiorne%dicactivi ty.
It arw should stteptitssepdate the: dose ~ received in normal ' ~ ~
aus.2 operation:activitiesc.in maintenance, in.radweste handling n a.
.. / ; ew. nwp,w;,..bw.E 2 nd disposal ets W W $. & M W V v '. J....
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~:..w e J11.5.1 n Designate the' person responsible for inplant radiation 3.
< v i.G A Wprotection and for implementing the proceduras that keep.W #.i -
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M. G.;
radiation: exposure below the applicabic711mits. Indicate '
T - who controls' access to the 'T.odistion Controlled Areas"'
.' M' _f and how this: control _.1s implem.nted.... -
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ill S lf Provide a'more detailed description of specific procedural or
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m Gn.c.M. equipment. techniques which will be used to obtain reduced iff TM overall plant.reci attenfexposure.D Describe any. techniques '
- 4, 7, 1Mte:be employed, suctas,prejob planning.and preparation,.use.
6 of exposure ~ allocations, administrative'expoure limits,
' - x'speciffc: job. training and, job debriefings -radiationarcrk.
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permits.:. removal of unnecessary sources of radiation' including
. 31ushing and decontamination, usa of recto handling devices
. and tt::r;orary shielding. Tho'eriteria for implementing various exposure reduction techniques should also be presented.
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i 111.5.3".DefiNethe'RadiatitiControlledArea.
L' hat procedures will he used to determine personnel access to areas vritMn the m
Radiation Centrolled Ares?
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11.5.6o t' hat criteria id11 he used to determine the ned fer nor'or:dna
. whole body counting ;nd bio-ascays? mint facilities ara
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avai.labic.for. this.ourpose?
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i Jacob Kastner, Chief, Radfological Assessment Branch
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Directorate of Licensino CC' ~ LiDenton ~
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