ML20009D403
| ML20009D403 | |
| Person / Time | |
|---|---|
| Site: | Westinghouse |
| Issue date: | 06/10/1981 |
| From: | Nardi A WESTINGHOUSE ELECTRIC COMPANY, DIV OF CBS CORP. |
| To: | Page R NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| References | |
| 19300, LA-81-114, NUDOCS 8107240033 | |
| Download: ML20009D403 (10) | |
Text
(90-057 LA 81-114 h
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Westinghouse Water Reactor f.3 9 55<355
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Electric Corporation Divisions
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PiffsbEEh PennsyNanta 15230 June 10, 1981 V
U.S. Nuclear Regulatory Commission Office of Nuclear Material Safety & Safeguards Division of Fuel Cycle & Material Safety
/^'i Washington, D.C.
20555 V
Attention: Mr. R. G. Page. Chief Uranium Fuel Licensing Branch Gentlemen:
SUBJECT:
Application for Amendmer.t to License SNM-1107, Docket 70-1151 The Westinghouse Electric Corporation hereby transmits an application for an amendment to License No. SNM-1107 for our Columbia, SC Plant. The purpose of this application is to revise the description of the use of Borosilicate -
glass raschig rings as a secondary method for nuclear criticality control.
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Enclosed is a check in the amount of $1,400 in payment of the fee requirement 4
specified in 10 CFR 170.31.
If you have any questions regarding this matter, please write me at the above address or telephone me at (412) 373,4652.
A. J. Nardi, Managee
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DOCKETO PPIiCant..,,
Check No.2h,;J'}'d
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Date Check Rec'd n gg MAIL SEcnog ll Received By
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SNM-1107 l
REVISION RECORD Revision Date of Pages No.
Revision Revised Revision Reason 11 6/24/530 102g Reprint Section 1.9.1.10 entitled
" Solution Storage" previously printed on page 102.
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l 11 6/24/80 154 Add the types of waste treatment conducted I
at the Columbia Plant.
12 6/1 0/81 60, 60a, Describe use and testing of raschig rings.
60b, 60c.
Provide test results on analysis of raschig 61 rings.
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12 6/10/81 1 01 Revise solution conditions.
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12 6/10/81 220 Specify minimum operating conditions for use of raschig rings.
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, ' bet 70-1151 Defe 8/24/74 Revision No.11 Date: 6/10/81 Pone 9 i
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SNM-1107 Page 10 intentionally left blank.
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Docket 70-1151 Date: 8/28/74 Revision No.12 Date:
6/10/81 Page 10
SNM-1107 1.8.1.2 (Continued) minimum of one foot edge-to-edge separation with no I
interaction considerations.
Dry 00 in closed containers -- Calculations for UF 2
6
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reported in K-1663 indicate that K. for U(5.0) F with an 6
235 H/
U $ 10 is less than 1.0.
Based on the nuclear similarity of oxygen and fluorine, and on the shape of the
, OV curve in Figure 3 of K-1663, this value is considered to apply to oxides of uranium enriched <4.15 w/o in the isotope 235, provided that H/U $ 0.5 and the moderator is uniformly U
distributed in the fissile material. Therefore cuch subcrits require no interaction considerations. However, individual containers must be closed or sealed and must meet one of the subcrit maximum permissible values established in subparagragh (h
Q l.8.1.1.
An array :nust provide a minimum of one foot edge-to-edge spacing between subcrits. These requirements assure nuclear criticality safety if a subcrit or the array were to be accidentally moderated." The same requirements apply to the oxides of uranium enriched between 4.15 w/o and 5 w/o in 235 the isotope U, except that the H/U ratio is linited to O
-< 0. 3.
1.8.1.3 Nuclear Poisons Borosilicate glass Raschig rings, when used as the primary l
l control for nuclear criticality safety, are used only in accordance with Regulatory Guide 3.1 "Use of Borosilicate -
Glass Raschig Rings as a Neutron Absorber in Solutions of Fissile Material." Raschig rings may also be used as a secondary control to provide additional nuclear criticality safety assurance in vessels of Docket 70-1151 Defer.8/28/74 Revision No.12 Defe: 6/10/81 Pose 60
SNM-1107 1.8.1.3 (Continued) uncontrolled geometry where normally uranium concentrations are maintained less than the maximum 235 permissible solution concentrations (5.0 g 0/ liter for aqueous solutions) as the primary nuclear criticality safety control. Typical of such uses would be the addition of Raschig rings into'the process quarantine tanks, which are sampled prior to release to the Waste Treatment Facility, and effluent scrubber system reservoirs.
The solutions used in these tanks have a pH <ll.0 and a fluoride c6ncentration of approximately 4% as NH F.
Ten 4
years of operating experience at the Columbia Plant has shown that corrosion of the rings is negligible as shown by the data given in table 1.8.1.1.
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O Docket 70-1151 Deem Revision No.12 Date: 6/10/81 Pone 60a
SNM-1107 1.8.1.3 (continued) f%Q The following tests are performed annually to determine the various parameters of the Raschig Rings. Test results are reported to the Radiation Protection Component for review and evaluation:
Settling The levels of rings in the tanks are determined by visual and physical measurements in accordance with written procedure. Rings are added when h) the required cumulative addition ' ill become equal' to 10% of the original w
loading. Since 1971,' settling of the rings has been negligible.
Physical Properties The volume occupied by the rings is determined by calculating the arith-metic difference between the actual tank volume and the liquid capacity of the tank with the rings. The glass content volume of the tanks is approximately 39%.
' Boron Content Boron con' tent is determined in accordance with Appendix A of ANSI /ANS-8.5-1979. Rings have been sampled and analyzed since 1971, with no significant boron leaching' detected. The, average boron content of the rings is approximately 12.5 weight percent B 0 '
23 A publication by N. Ketzlach entitled " Proposed Extension of Raschig Ring Standard to Low Enriched Uranium Fuels," concludes that a 24 volume % borosilicate glass Raschig Ring poisoned mixture ( <5% U-235 enriched) cannot be made critical in the glass is 12.8%. Reducing independent of uranium concentration when B 023 the B 0 content in the glass to 11.8% with 5.49 U/ml in the matrix solution 23 resulted in an increase of-3.3% in the calculated Km compared to the Km for j
12.8 8 0. The average B 0 content of rings in the tanks is approximately 12.5%.
23 23 Consequently, the mixture is safe (K m< 0.8). Actually, tne margin of safety is much greater since the concentration of 5.4 g U/ml
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- Dockee.70-1151 Dafor 8/18/74 Revision No.12 Date: 6/10/81 Pose 60b
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TABLE 1.8.1.1 RASCHIG RING ANALYSIS FOR QUARANTINE TANKS f
Weight Percent B 023 f
Avg.
3/1/71 3/1/J1 2/15/]2, 11/15/72 1/23/75 7/1/75 12/29/75 7/15/76 1/5/77 6/21/77 3/3/78 6/5/78 11/1/78 11/13/79 5/20/80_.5/20/80 g
_ il6A 12.9 11.45 12.34 12.27, 12.80 12.67 13.00 13.02 12.66 12.0 12.5 12.0 12.7 -
12.5 l,
s <1to 11.3 12.04 12.37 12.79 12.93 13.17 13.06 13.21 12.3 12.3 12.2 12.8 12.5 h
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.M 10.2 12.90 12.90 12.22 12.62 12.76 12.67 12.11 12.94 12.1
-12.1 11.9 12.7 12.3 r
Y s.!A 12.4 12.5 12.49 12.99 12.37 12.62 12c44 12.80 12.73 13.22 12.1 12.6 12.1 12.6 12.6
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N V-216B 13.2 12.7 12.80 12.22 12.80 12.72 12.79 12.59 12.88 12.1 12.0 11.9 12.7 12.6 O
%-216C 11.4 12.6 11.53 12.52 12.46 13.34 12.46 12.77 13.26 12.96 12.1 12.6 12.2 12.5 12.5 i
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12.4 12.0 l
g Unused Ring 10.8 13.4 12.99 t
Unused Ring 10.6 m
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SNM-1107 4
l<8.1.3 (Continued) is greater than the solubility limit for uranium in solutions.
In addition, the average volume occupied by the rings in the existing tanks is approximately 39 volume %.
The use of any other nuclear poisons or any use of poisons for primary criticality control ret. ires a specific license amendment.
1.8.1.4 Nuclear Interaction Evaluations All subcrits must meet the MPV's and must have a separation of at least one foot edge-to-edge between any two subcrits.
Interaction between subcrits which are not isolated (1 2.1.1) is evaluated using the surface density method.
This method requires that each subcrit be limited to the nuclear equivalent of a sphere having,< 0.4 times the volume of an unreflected critical sphere of the same material
( _< 0.4 " fraction critical"). Value1 are esublished for each control using equal buckling conversions as follows:
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(R
)2 I +2At)2 + (1.+2At)2+ (TPdTt)2 1
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a for a.31ab
+A T
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with finite dimensions, or O
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O Docket 70-1151 Dafw 8/28/74 Revision No.12 Date: 6/10/81 poo. 61
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SNM-1107 2.3.2.2
'(continued) e.
Subcrits which are safe by concentration control and which are part of a continuous processing line will be filed with a glass volume fraction of at least 30% Borosilicate glass Raschig Rings. The Raschig Rings shall be purchased in accordance with the specifications listed in ANSI /ANS-8.5-1979. During operation the glass Raschig Rings will be exposed to 'a basic solution '(NH 0H) which will have a 4
pH'less than 11.0, temperature of 60 C or less, and a fluoride concentration of # 4%. The Raschig Rings shall be acid washed on a routine basis with a weak acid solu-tion containingel5 - 30% nitric acid. The Raschig Rings shall be inspected at least once per year for (1) settling, (2) physical properties and (3) boron content in accordance with ANSI /ANS-8,5-1979, "Use of Borosilicate-Glass Raschig
' Rings as A Neutron Absorber in Solutions of Fissile Material."
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Subcrits composed of f.uel assemblies will be limited by reactivity. The computed keff, including allowanced for computational error, will not exceed 0.95.
These compu-tations will be perfonned by the NFD, Nuclear Design Department using procedures such as MUFT, SOFOCAT, LEOPARD, and/or PDQ-03. The results of these computations will be independently reviewed within the dept tment and approved by the department manager before being transmitted to the NFD Manufacturing Department.
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Maximum permissible values for subcrits containing plutonium will be those established in Figure 2.3.2.5.
Subcrits containing plutonium will be restricted to encapsulated components containing Pu02 mixed with natural or depleted UO Docket 70-1151 Dafee 8/24/h4 Revision No.12 Date: 6/10/81 Pone 220
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TABLE 1.8.1.1 RASCHIG RING ANALYSIS FOR QUARANTINE TANKS; Weight Percent B 023 s
Avg.
3/1/71 3L1/71 2/15/72'11/15/72 1/23/75 7/1/75 12/29/75 7/15/76 1/5/77 6/21/77 3/3/78 6/5/78 11/1/78 11/13/79' 5/20/80 5/20/80 ~
1 V-Il6A 12.9 11.45 12.34 12.27 12.80 12.67 13.00 13.02 12.66 12.0 12.5 12.0
.12.7 12.5 V-Il68 11.3 12.04 12.37 12.79-12.93 13.17 13.%
13.21 12.3 12.3:
.12.2
'12.8 12.5
- 2 V-Il6C 10.2 12.90 12.90
-12.22' 12.62 12.76 12.67 12.11 12.94 12.1 12.1 11.9 12.7 12.3 9
V-216A 12.4 12.5 12.49 12.99 12.37 12.62
- 12. 12.80 12.73
'13.22 12.1 12.6 12.1 12.6 12.6 V-2168 13.2 12.7 12.80 12.22 12.80 12.72 12.79 12.59 12.88 12.1 -
12.0 11.9 12.7 12.6 l
O V-216C 11.4 12.6 11.53 12.52 12.46 13.34 12.46 12.77 13.26 12.96 ' 12.1 12.6 12.2 12.5 12.5 Unused Ring 10.8 13.4 12.99 12.4 12.0 l
y Unused Ring 10.6 a
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