ML20198D239
| ML20198D239 | |
| Person / Time | |
|---|---|
| Site: | 07001113 |
| Issue date: | 05/12/1992 |
| From: | Winslow T GENERAL ELECTRIC CO. |
| To: | Jim Hickey NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| References | |
| NUDOCS 9205190242 | |
| Download: ML20198D239 (11) | |
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GE Nuclear fwyy
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I May 12, 1992 Director Office _of Nuclear Material Safety and Safeguards U.S. Nuclear Regulatory Commission Washington, D.C.
20555 Attention:
Mr. John W.
N..
Hickey, Chief Fuel Cycle Safety Branch OWFN, Room GH6, Mail 6H3
Dear Sir:
Subject:
License Amendment Request, Revision 35 (This is additional information provided to the 2/14/92-submittal)
References:
- 1) NRC License, SNM-1097, Docket-70-1113
^) Amendment, TP Winslow to CJ Haughney, 2/G/91
- 3) Amendment, TP Winslow to JWN Hickey, 2/14/92 W3.th reference to activities authorized by NRC License SNM-1097 at-the General Electric Company Nuclear Fuel and Components Manufacturing - (NF&CM); facility, GE requests approval for the
. enclosed page additions hereby submitted for Part IIlof our current license demonstration application.
This1 request.provides additional'information in Part IILof our license amendment application-for-criticality safety,.-taking.
L credit for'the absorption in. neutron poisons as allowed in Section-L 4.2.4.4 of Part I of'the license.
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9205190242 920512 PDR ADOCK 07001113 q g g,;
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Mr. JWN Hickey I
May 12, 1992 Page 2 1 contains an explanation of the additions by page.
Attachment contains the page additions to the license demonstration in Part II of our current application.
II All the additions provided to the license demonstratian in Part are indicated with an asterisk in the right hand column of the page.
Please contact me at (919) 675-5461 if you would like to discuss this matter further.
Sincerely, GE NUCLEAR ENERGY
$A4-To T. Preston Winslow, Manager Licensing & Nuclear Materials Management
/sbm Attachments cc:
TPW-92-072 a
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.m Mr. John'W. N. Hickey
='May 12, 1992
-Page_1 of 1 ATTICHMENT 1 DESCRIPTION OF REQUESTED REVISIONS l
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Section Description 16.79-16.19 Added to provide explanations for the 16.83 critica13ty safety, taking credit for absorption in rautron poisons as allowed in Section 4.2.4.4 of Part I of the license.
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Mr.' John W. N. Hickey May.12,.1992 i
Page-1 of 1 4
ATTACHMENT-2 i-9-
PAGE ADDITIONS-TO THE LICENSE. REVISION BY PAGE AND THE i
DEMONSTRATION (PART II) 4 c
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REVISIONS BY PA,GE Application Application Application Page Date Page Date Page Date TABLE OF CONTENTS I-1.21 5/16/88 I-3.3 10/23/87 I-1.22 I-3.4 1
10/23/87 I-1.23 I-3.5 2
I-1.24 I-3.6 3
I-1.25 I-3.7 4
I-3.8 5
I-3.9 6
CHAPTER 2 I-3.10 7
I-3.11 8-5/12/92 I-2.1 2/06/89 I-3.12 9
10/10/91 1-2.2 I-3.13 10 4/16/92 -
I-2.3 I-3.14 il 2/06/89 I-2.4 I-3.15 12 5/12/92 I-2.5 I-3.16 I-2.6 I-3.17 1/22/92 1-2.7 I-3.13 I-2.8 I-3.19 PART I I-2.9 I-3.20 I-2.10 I-3.21 I-2.11 I-3.22 CHAPTER 1 I-2.12 I-3.23 I-2.13 I-3.24 I-1.1 5/16/88 I-2.14 I-3.25 I-1.2 I-2.15 I-3.26 I-1.3 I-2.16 I-3.27 I-1.4 10/22/91.
I-2.17 I-3.28
-I-1.5 5/16/88 I-2.18 I-1.6 I-2.19 I-1.7 12/03/90 I-2.20 I-1.8 5/16/88 I-2.21 CHAPTER 4 I-1.9 I-2.22 I-1.10 I-2.23 I-4.1 10/23/87 I-1.11 I-2.24 I-4.2 I-1.12 I-2.25 I-4.3 I-l'13 I-2.26 I-4.4 4.
I-1.14 I-4.5 I-1.15
'I-4.6 I-1.16.
I-4.7 I-1.17 CHAPTER 3 I-4.8 I-1.18 I-4.9 I-1.19
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I-3.1 10/23/87 I-4.10 I-1,20 4/16/92 I-3.2 I-4.11 i;
LICENSE SNM-1097 DATE 5/12/92 Page DOCKET-70-1113 REVISION 35 I i
_n__.________________
l RSVISIONS BY PAGE Application Application Application Page Date Pace Date Pace Date II-15.18 9/30/83 II-16.8 9/30/83 II-16.50 2/06/91 II-16.9 II-16.50.1 2/06/91 II-15.19 II-16.50.2 2/06/91 II-16.10 II-15.20-II-16.50.3 2/06/91 II-16.11 II-15.21 II-15.22 II-16.12 II-16.50.4 2/06/91 II-16.13 II-16.50.5 2/06/91 II-15.23 II-16.51 2/06/91 II-16.14 II-15.24 II-16.52 9/30/83 II-15~.25 II-16.15-II-16.53 11-16.16 II-15.26 11-16.54 II-3A.17 11-15.27 II-16.55 II-15.28 II-16.18 II-16.56 II-16.19 II-15.29 II-15.30 II-16.20 II-16.57 II-16.58 II-15.31 II-16.21 II-16.59 II-16.22 II-15.32 II-16.60 II-16.23 II-15.33 II-15.34
-II-16.24 II-16.61 II-16.62.
II-16.25 l
II-15.35 11-16.63 II-16.26 11-15.36 II-16.64 II-16.27 II-15.37
'II-16.28 II-16.65 10/10/91 II-15.38 II-16.66 II-16.29 II-15.39:
II-16.67 II-16.30 II-15.40 II-15.41 II-16.31 II-16.68
.II-15.42 II-16.32 II-16.69 II-16.70 II-16.33 II-15.43 II-16.71 II-16.34
-II-15.44 II-16.72 Il-15.45-II-16.35 II-16.73 II-15.46 II-16.36 l
II-15.47 II-16.37 II-16.74 II-16.75
-II-16.38 1I-16.76
-II-16.39-II-16.77 II-16.40 II-16.78 CHAPTER 16 II-16.41 II-16.79 5/12/92 II-16.42 II-16.1 9/30/83-II-16.43-II-16.80 11-16.2 II-16.44 II-16.81 II-16.82 II-16.45 II-16.3 II-16.83 II-16.4 II-16.46 II-16.47 II-16.5 II-16.6 11-16.48 2/06/91 CHAPTER 17 II-16.7-II-16.49. 2/06/91 11-17.1-7/25/83
....n LICENSE
'SNM-1097 DATE 5/12/92 Page DOCKET 70-1113 REVISION 35.
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A 16.19 NUCLEAR POISONS In some cases, criticality safety analyses have taken credit for absorption in neutron poisons as allowed by Section 4.2.4.4 of the license.
Application of the license requirements for thaca cases is summarized as follows.
16.19.1 Fluoride Waste Slab Tanks The fluoride waste slab tanks consist of 10' x 20' tanks having a nominal thickness of 5.5".
Each tank is approximately centered in an 18" wide gap between two 10" thick concrete slabs.
To demonstrate that this
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array is a safe geometry for UO 1
2 at ortimum moderation, poison panels were installed on both sides of each tank.
These panels consist of a 20 mil thick sheet of cadmium
<.Td a one inch sheet of polyethylene completely encased in.065" thick s*.ainless steel.
License conditions are satisfied as follows:
a - The fixed neutron absorber is elemental cadmium.
The cadmium and polyethylene cre sealed in a.065" thick stainless steel cladding.
Each panel is 40" x 94" and is held in position by the steel framework used to prevent the tanks from
" bulging".
There are six panels edge-to-edge across the width of one tank.
f LICENSE SNM-1097 DATE 5/12/92 Page DOCKET 70-1113 REVISION 35 l
II-16.79 i
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The cadmium sheets were certified by the vendor and the thickness was verified on site.
Edges of the l
cadmium sheets have 90' degree bands which are embedded in the polyethylene to fix their location.
Each complete panel was verified by neutron transmission measurementa and stamped vith an arrow pointing to the poison side.
Quality assurance was provided by the quality organization.
Records are
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maintained under FCR 10.900.
The inside thickne.ss of the clad enclosure is 1.07"
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scures a close fit at the edges.
The structural framework helps to ensure this close fit over the area of the panels.
Calculations were performed using the GEMER Monte Carlo Code which is ideally suited to heterogeneous systems.
Results of specific calculations with cadmium from the general validation were used to assure a conacrvative calculational bias.
There are no significant flammable materials in the slab tank room except for the polyethylene in the poison panels.
Only " wet" oper&tions occur in this room.
The effectiveness of the poison is routinely measured on a biennial basis by neutron reflection L
measurements.
The neutron source and reflector are both placed between the tank and the panel.
These
-measurements have considerable variance and are trended against previous measurements.
w LICENSE SNM-1097 DATE 5/12/92 Page DOOKET 70-1113 REVISION 35 1
II-15.80 l-Lo l'
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tie poison panels are not removed.
The adequacy of the panels under accident conditions are calculated in a separate technical report which is included with FCR 80.900.
16.19.2 Poison Panels on Annular Vessels The uranium recovery operation employs 29 annular vessels for storing / processing uranium storage.
These vessels are safe geometries based on inner and outer annular borated poison panels.
These panels are encased in stainless steel cladding.
i License conditions are satisfied as follows:
n The fixed neutron absorber is a stable compound of boron.
The borated polyethylene panels are sealed in a stainless steel cladding.
The panels are held in place by the support framework a
cf the vessels.
The panels cannot be removed intact with the vessels in their vertical positions.
The boron content in each panel is certified by the vendor and supported by detailed neutron reflector measurements.
Inspection re?ords are maintained within FCR 90.161.
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an-LICENSE SNM-1097 DATE 5/12/92 Page DOCKET 70-1113 REVISION 35 II-16.81
'9 The inside thickness of the clad enclosure is 0.1875" larger than the panel.
The panel is one piece and not subject to rearrangement unless melted.
Calculations were performed using the GEMER Monte Carlo Code which is ideally suited to heterogeneous systems.
Results of specific calculations with boron from the general validation were used to assure a conservative calculational bias.
The annular vennels are located in the " wet" areas of UPMP.
The greatest risk of fire is in the SX cell where significant quantities of N-dodecane are used in the process.
However, each vessel has a cecond control to assure its safety in the event of a geometry failure.
The effectiveness of the poison is routinely verified on a biennial basis by neutron reflection measurements.
The neutron source and detector are both placed between the tank and the panel.
These measurements have considerable variance and are trended against previous measurements.
The poison panels are not removed.
16.19.3 Primary HEPA Filters Primary HE?A filters are used to remove particulate uranium compounds from the exhaust of equipment processing dry powder.
Safety is based on a limit on L
the delta pressure across the filter and the correlation
_m LICENSE SNM-1097 DATE 5/12/92 Page
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DOCKET 70-1113 REVISION 35 II-16.82 s
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between delta pressure and mass.
This is used to limit the primary filter housing to a safe mass of 00.
A 2
second control is based on the moderation limit in dry areas.
However, many of these filters are located in areas that process moderated materials or may under i
upset conditions.
A geometry control is used in these
'ased on the filter dimensions and the boron area naturally-present in the media.
To use this control, the boron conten'..nust be certified by the vendor.
The Boron 10 isotope content of new media shall be representatively checked at least annually.
If the media is not present, the filter is not present
)
and uranium will not be held up in the filter housing.
If the filter media is removed during operction (e. g.,
fire) there will be no further holdup of uranium.
The uranium present at the time of the filter failure will be limited to a safe value, independent of separation of the uranium and boron, by the delta pressure control described earlier.
Filter calculations may be performed with the GEKENO.4 Monte Carlo Code because of the homogeneous distribution of the boron without the filter.
However, limiting cases are performed with GEMER.4 since available critical experiments use heterogeneous fuel.
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i LICENSE SNM-1097 DATE 5/12/92 Page L
DOCKET 70-1113 REVISION 35 II-16.83
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