ML19305B655
| ML19305B655 | |
| Person / Time | |
|---|---|
| Site: | Framatome ANP Richland |
| Issue date: | 02/18/1980 |
| From: | SIEMENS POWER CORP. (FORMERLY SIEMENS NUCLEAR POWER |
| To: | |
| Shared Package | |
| ML19305B652 | List: |
| References | |
| 15618, NUDOCS 8003200037 | |
| Download: ML19305B655 (6) | |
Text
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. J-(a) The absorbers' are an integral part of the equipment structure.
(b) Inspection shall verify that absorber structures are intact and an integral part of the structure at least monthly.
(c) The array or process to be controlled cannot be assembled or performed in alternate equipment not containing absorbers.
5.2.2.4 Concentration Control Reliance for primary criticality control may be placed o'n concen-tration controls in areas where geometry control is not practicable,
- and where the nature of the process and operations make violation of the concentration limit unlikely even af ter failure of any single control.* Concentration control may be applied to both overmoderated and undermoderated accumulations of material as
- described below.
- 5.2.2.4.1 Concentration control - Solutions-The concentration of fissile material dispersed or dissolved in another =edium may be limited to prevent criticality, provided that:
/a) The permitted concentration of fissile material in solution shall be equal to or less than fif ty percent
, f of the mini =um critical concentration in the vessel.
(b) -The system full of material at the maximum allowable concentration shall have a k,gg <0.95.
(c) For individual tanks (non-geometrically safe) using
.. concentration control, the mass shall be limited such i
that k,ff 10.95 for the caximum uranium mass accumulated i
in the tank under the worst conditions attainable by inadiertent concentration of the fissile material. For large storage systems where concentration of the fissile material is not a credible condition, or where admini-strative practices are implemented to prevent concentra-tion of the fissile material, the above require =ent may i
be disregarded.
8003200 Ucense No.
SW-1227 Docket No.
70-1257
- w Ne I-S.2.2.4.1 I-4.2.2.4; I-5.29 I-5.2.2.4.1 18 February 1980 Amends Sect. W Amend Na '
Date
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5.2.2.4.2 concentration control - Powders and Pellets
,y The concentration of hydrogenous material within the fissile mater-ial may be limited to a small percentage by weight of the fissile material (moderation control) to prevent criticality, provided that:
(a) The permitted concentration of hydrogenous material shall be equal to or less than fif ty percent of the critical concentration for the system in question;*and*
(b) The system full of the material in question, under the worst credible accident conditions, shall have a k,fg
<0.95;,*and*
(c) *Where practicable,*the material shall be contained within a fireproof barrier or a process area containing linited sources of hydrogenous material. *In the absence of a fire-proof barrier, special controls shall be used to prevent fires and to centrol the use of moderators in firefighting in such process areas.*
5.2.2.5 Critical values Safe limits shall be determined fro: critical values as described in Sections 5.2.1.4(a), and 5.2.2.2(a), (b) and (c). The technical bases for the critical values are as fo11cus:
.(a) Enrichment Lovel
[, ' The UO Plant is designed to be critically safe for 5% U-2
~235 enrichment. All equipment that is designed to assure criticality safety by geometry control shall be safe at 5% U-235. All process steps where uranium is
' normally moderated shall be goemetrically safe at 5: U-
~ 235 enrichment. Where batch control is utilized in other process steps, enrichment level 1:mits shall be clearly posted on all process equipment and storage racks.
(b) Data Where applicable data are available, critical values shall be based on experimental data.
In the absence of direct applicable experimental measurements, critical. values shall be derived frea calculations i
l Page License No.
mW Decket No.
70-1257 Sect. N o.
T-5. 2. 2. 5 I-5.2.2.4.2; Amend Na 18 Date February 1930 Amends Sect. (si I-5.2.2.5 I-5.30
e mP
. L 4.6.13 Conversion Process Liquid Effluent Ion Exchange Treatment Systems 4.6.13.1 System Description Effluents from the polishing centrifuges are collected in the quarantine tanks located in the tank gallery, where samples are withdrawn to check the uranium content both visually and with an on-line uranium monitor. If the effluent contains greater than 300 ppm uranium, it will be recycled.
If it contains 300 ppm uranium or less, the effluent will be pumped through a set of prefilters and then through ion exchange columns for further uranium removal. A turbidity meter in the feed line to the ion exchange system 'will alarm and stop the flow to the columns at a point representing 300 ppm uranium. Each ion exchange system consists of three 20 inch diameter by 10 feet long cylindrical tanks, each approxi=ately half full of resin. The effluent will pass through two tanks in series and then be discharged through the 5.'" Accountability Measurement Station to the Process Chemical Waste e orage Lagoon System'. The effluent frem the first ion exchange column passes through an on-line uranium monitor to detect saturatien of the ion exchange resin. When the ion exchange resin becomes :sturated to a point where uranium begins to leak through (breakthrough), the colu=n is taken off line for regeneratien. The resin is regenerated by first eluting the uranium off the resin with less than 2N nitric acid, then the resin is reconditioned with aqueous ac=onia. The uranium rich cluste will be stored in eluate storage tanks located in the ion exchange regeneration tank gallet,.
4.6.13.2 Assumptions for Analysis The analysis considers the four following modes of operation of the ion exchange columns:
(a) !!ormal Ooerating Condition (Loaded Column)
The bottom half of the colu=n contains resin loaded with
- 3*
uranium to a bulk density of approximately 0.6 kgs/f t The l
top half of *:he column contains effluent at the =aximum permissible release Itait (300 ppm U).
%nse No.
SNM-1227 cocket No.
70-1257 Rect.Na IT l.,6.13,3 New II-4. M February 1980 3% ge g unend Na 18 na
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(b) Elution of Normal Operating Condition The total content of the column accumulates in the most reactive geometry considering the maximum uranium concen-tration for 2N nitric acid and the geometry of the column.
(c) Maximum Credible Accident Condition The bottom half of the ion exchange column contains the
~
resin bed packed with ADU in the interstitial volume of the resin bed. The upper half of the column contains ef fluent at the m=v4~"= permissible release limit (300 ppm U).
(d) Elution of Maximum Credible Accident Condition The total cIsntent of the column accumulates in the most reactive gecmetry considering the maxi =um uranium concen-tration for 2N nitric acid and the geometry of the column.
Since the czaximum uranium concentration of 2N nitric acid is less than the uranium concentration for the maximum credible accident, the elution cycle wi'.1 decrease the uranium concentration instead of increasing it.
4.6.13.3 Evaluation (a) Normal Ooerating Condition for a Loaded Column
- Ihe nor=al operating condition will assume that the resin
'is loaded to the max 1=um resin loading value which is calculated in the following manner:
Ato Weight
-grams / liter = equivalent / liter X Total Chelating / Cation Exchange Capacity: 5.3 meg /g(dry)
' Moisture Content:
68 percent (nominal) 0.67 kg/i Shipping Weight (sodium form) = 42 lbs/f t
=
Resia dry weight: 0.67 kg/L x 0.32 = 214 g/L 5.3 meg /g x 214 g/i = 1134.2 meg /L = 1.134 eq/I 1.134 eq/1 x
= 45 g/L 6
.. Use a resin loading value of 50 gm U/ liter
- Ucense No.
%N-1 " 7 Docket No.
70-1'97 Sect. No. T T _ t c,e,
5E, Amend Na 18 Date Februarv lo80 Amends Sect. (si New II-4.77
[.. ' '.
f.
6 9
- g
. L Minimum critical and safe uranium concentrations for a twenty inch diameter tank:
Minimum Critical Concentration = 27.7 kas U/ft(*}
- = 12.7 kgs/ft 448 gm U/1
=
Safe Concentrate (50% of Critical) = 224 gm U/1 The maximuq operating concentration of 50 gm U/t is less than 50% of the safe concentration (224 gm U/1).
/s 4 w.
4 4 -
e l
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1 15E13 License No.
SNM-1227 nocket No.
70-1257 Sect. No. II-4. 6.13. 3 Amend Na 1R Date Whmam 1900 Amends Sect. (s)
Wu~
II.4.77a A
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