ML20147C108

Application for Amend to License SNM-1067,authorizing Increase in Weight Percent of Enriched U from Less than 4.1% to Less than 5% U-235.Fee Paid

ML20147C108
Person / Time
Site:	07001100
Issue date:	01/20/1988
From:	Mcgill P ABB COMBUSTION ENGINEERING NUCLEAR FUEL (FORMERLY
To:	Rouse L NRC
Shared Package
ML20147C114	List: LD-88-014, Forwards Fee for 880120 Application for Amend to License SNM-1067,increasing Weight Percent of Enriched U That Can Be Processed at Facility ML20147C108
References
28965, NUDOCS 8803030006
Download: ML20147C108 (96)

Text

_ _ _

k p

.Y'!

- 0 3%ss % y ~.g l

':, &y y:

9 a, }x o

4

( ',

6 Soft 150STION ENGINEERING 4;u

.4 4 January 20, 1988 N'

p,hI d6'/,,

License SNM-1067 Docket 70-1100 Fy /p[j;p%

cC J

Mr. L. C. Rouse, Chief

, q ~l a,..j

,i; 2

?

7, Fuel Cycle Safety Branch J

Division of Fuel Cycle, Medical, s

~,

~

Academic and Commercial Use Safety y

U.S. Nuclear Regulatory Commission x

washington, D. C. 20555

Subject:

License SNM-1067 Amendment Request

Dear Mr. Rouse:

This letter requests Nuclear Regulatory Commission approval of an amendment to the Combustion Engineering Windsor Fuel Fabrication Facility license (SNM-1067).

The supporting documentation for this amendment request is provided in the Enclosures to this letter.

The purpose of the subject amendment is to increase the weight percent of enriched uranium that can be processed from <4.1 % to <5.0 % U235 Enclosure (1) provides a tabulation of affected pages and their respective revision numbers.

Enclosure (2) provides the proposed change pages supporting our amendment request.

Three copies of the enclosures are j

included herewith for your use in evaluating our request.

A check in the amount of $150.00 to cover the license change application fee, as required by 10CFR170.31, will be forwarded under separate cover to the License Fee Management Brat -t.

If I can be of further assistance, s) please advise.

I J {M ff.1-)..___.---..

Very truly yours, i M 'f).

I--

COMBUSTION ENGINEERING, INC.

[JSD

..6 fji3 JK1 h(k' gr/y/

$, NhW yd T. L. McGill'

/

Vice President b

M{"I Nuclear Fuel PLM:ss

Enclosures:

As Stated Power Systerns 1000 Pro @ect H.ti Road (203) 683-1911 Combustcn Eng:neenng. Inc.

Post ONce Box 500 Te:ex 99257 Winds r, Connectcut 06095 0500 8803030006 000120 PDR ADOCK 07001100 C

PDR

~

Docket No. 70-1100 SNM1067 ENCLOSURE 1 COMBUSTION ENGINEERING, INC.

WINDSOR FUEL FABRICATION FACILITY REQUEST FOR LICENSE AMENDMENT LIST OF AFFECTED PAGES I

l E

I i

i JANUARY', 1988 1

i l

l 1

WINDSOR FUEL FABRICATION FACILITY REQUEST FOR LICENSE AMENDMENT Combustion Engineering requests that the license (SNM-1067) fer its Windsor Fuel Fabrication Facility be amended to increase the weight percent of enriched uranium that can be processed from

$4.1% to $5.0%.

The license pages affected by this amendment and their respective revision numbers are listed below.

The proposed change pages are provided in Enclosure 2.

Deleted Pace Added Pact Pace No.

Egy.

Pace No.

Egy.

I.1-2 5

I.1-2 6

I.1-3 5

I.1-3 6

I.3-9 6

I.3-9 7

I.4-3 5

I.4-3 6

I.4-4 4

I.4-4 5

I.4-5 3

I.4-5 4

1.4-7 3

I.4-7 4

I.4-7A 0

I.4-7A 1

I.4-8 2

I.4-8 3

I.4-9 2

I.4-9 3

I.4-10 2

I.4-10 3

I.4-12 4

I.4-12 5

I.4-13 3

I.4-13 4

I.4-14 4

I.4-14 5

I.4-15 4

I.4-15 5

I.4-16 4

I.4-16 5

I.4-19 0

I.4-19 1

II.1-6 3

II.1-6 4

II.7-1 2

II.7-1 3

II.8-1 2

II.8-1 3

II.8-2 2

II.8-2 3

II.8-3 2

II.8-3 3

II.8-3A 0

II.8-4 2

II.8-4 3

Deleted Pace Added Pace Pace No.

Rev.

Pace No.

Rev.

Il.8.5 3

II.8 4 II.8-6 3

II.8-6 4

II.8-6A 0

II.8-7 2

II.8-7 3

II.8-8 2

II.8-8 3

II.8-9 2

II.8-9 3

II.8-10 2

II.8-10 3

II.8-11 2

I1.8-11 3

II.8-12 2

II.8-12 3

II.8-13 2

II.8-13 3

II.8-14 2

II.8-14 3

II.8-15 2

II.8-15 3

II.8-16 2

II.8-16 3

II. 8-l'/

3 II.8-17 4

II. 8-18 4

II.8-18 5

II,d-19 2

II.8-19 3

II.8-20 2

II.8-20 3

II.8-21 3

II.8-21 4

II.8-21A 0

II.8-22 3

II.8-22 4

II.8-23 2

II.8-23 3

II.8-23A 0

II.8-24 3

II.8-24 4

II.8-25 3

II.8-25 4

II.8-26 2

II.8-26 3

II.8-27 3

II.8-27 4

II.8-28 3

II.8-28 4

II.8-28A 0

II.8-28A 1

II.8-29 2

II.8-29 3

II.8-30 2

II.8-30 3

II.8-31 2

II.8-31 3

II.8~31A 0

II.8-31B 0

II.8-31C 0

II.8-32 2

II.8-32 3

II.8-33 2

II.8-33 3

I I'. 8 - 3 4 2

II.8-34 3

II.8-35 2

II.8-35 3

II.8-36 2

II.8-36 3

II.8-37 2

II.8-37 3

II.8-38 2

II.8-38 3

II.8-39 2

II.8-39 3

II.8-40 2

II.8-10 3

II.8-41 2

II. 8 -- 41 3

II.8-42 2

II.8-42 3

II.8-43 2

II.8-43 3

Deleted Pace Added Pace Pace No.

Rev.

Pace No.

Rev.

II.8-44 2

II.8-44 3

II.8-45 2

II.8-45 3

II.8-46 2

II.8-46 3

II.8-47 2

II.8-47 3

II.8-49 2

II.8-48 3

II. 4 -49 2

II.8-49 3

II.J-50 2

II.8-50 3

II.8-51 2

II.8-51 3

II.8-52 2

II.8-52 3

II.8-53 3

II.8-53 4

II.8-54 2

II.8-54 3

II.8-55 2

II.8-55 3

II.8-56 2

II.8-56 3

II.8-57 2

II.8-57 3

II.8-58 2

II.8-58 3

Docket No. 70-1100 SNM-1067 ENCLOSURE 2 COMBUSTION ENGINEERING, INC.

WINDSOR FUEL FABRICATION FACILITY REQUEST FOR LICENSE AMENDMENT PROPOSED LICENSE CHANGE PAGES l.

I JANUARY, 1988 l

l l

l.3 License Number Activities are covered by the License SNM-1067; Docket 70-1100.

1.4 Possession Limits & Locatign Combustion Engineering, Inc., requests authorization to receive, use, possess, store and transfer at its Windsor site, the following quantities of radioactive materials.

Isotope Form Ouantity Location 1.) Uranium enriched Uranium 500,000 Kg U Manufacturing-Bldgs.

to <5.0% weight Oxides

1. 17 & #21 & storage in percent U235 trailers adjacent to Bldgs. #17 & #21. Bldgs 1,

lA, 2, 2A, 3,

3A, 5,

6, 16 and 18.

35 2.) Uranium enriched Any 4800 gms U Bldg.

1, lA, 2,

2A, 3,

to less than 20 3A, 5,

6, 16, 17, 18 &

weight percent 21 (Bldg. 17 & 21 U235 limited to 350 gm U235 each for enrichments exceeding 5.0 weight percent U235).

3.) Natural and/or Any 10,000 KgU Bldg.

1, lA, 2, 2A, 3, Depleted Uranium 3A, 5,

6, 16, 17, 18,

& 21.

4.) Pu238 Encapsul-5 sources, each Building #17 ated containing less Neutron than 2.0 gm Pu238 Sources 5.) Pu Any Form 160 micrograms Bldg.

1, lA, 2,

2A, 3,

as analytical 3A, 5,

6, 16, 17, 18 samples

& 21 6.) Encapsulated U0 20 sources, each Bldg.

1, lA, 2,

2A, 3,

38 Neutron Sources containing 3A, 5, 6, 16, 17, 18 1.7 gm U235

& 21 7.) Uranium enriched Residue 1000 gms U235 Windsor Site to or greater than 20 weight percent U235 s

License No. SNM-1067, Docket 70-1100 Rev. 6 Date: 1/20/88 Page: I.1-2

1.5 Dnfinit19.Ds Any defin'itions which are not defined in standard references (e.g.,

ANSI-N-1.1-1976, "American Standard Glossary of Terms in Nuclear Science and Technology" or Title 10 of the Code of Federal Regulations) or that are unique to activities described in this license applications shall be defined where first used in the application.

1.6 Authorized Activities The primary activities carried out in buildings at the Windsor site include, but are not limited to the following:

Bldg. #1 & 1A -

Storage and use of small quantities of Radioactive Material ($700 GMS U235)

Bldg. #2 & 2A -

Product Development Activities.($700 GMS U235)

Bldg. #3 & 3A - Storage of small quantities of Radioactive Material

($700 GMS U235)

Bldg. 5 - Product Development Activities.

Bldg. 6 - Waste water processing from manufacturing and product development activities.

Bldg. 16 -Product Development Activities (5700 GMS U235)

Bldg. 17 -Manufacture of fuel assemblies utilizing low enriched uranium (up to 5.0 weight percent U235) in the form of uranium oxide powder, pellets, rods, and in assemblies.

Bldg. 18 -Product Development Activities ($700 GMS U235)

Bldg. 21 -Storage of SNM in shipping containers.

Windsor Site - Residue from prior operations, not to exceed 350 gms U235 in any one location.

Additional locations to be separated from one another by a minimum of 12 feet.

1.7 Exemotions and Soecial Authorizations Licensed activities in Bldgs.

1, lA, 2,

2A, 3, 3A, 5,

6, 16 and 18 shall License No. SNM-1067, Docket 70-1100 Rev. 6 Date: 1/20/88 Page: I.1-3

first bank of absolute filtors.

The pressure drop for all systems shall be checked monthly and documented.

When the face velocity at a ventilated hood drops below 100 fpm, the hood filters or ventilation system fil.ters will be changed, brushed, or knocked down to increase the air flow to 100 fpm minimum or the hood will not be used to handle radioactive material.

Face velocities will be checked monthly in Product Development.

The filters in these stacks shall be tested either by 1) counting samples immediately after 1/2 hour of operation or 2) DOP testing the filters in accordance with ANSI standards. Such testing shall be done after all filter changes or movement of the filters to assure they are adequately filtering the exhaust air.

The results of these tests shall be documented.

Each ventilating filter system described in Section 3.2.3 shall be equipped with an instrument that measures the pressure drop continuously.

• 3.2.4 Instrumentation Capabilities of radiation detection and measurement instrumentation shall be as follows:

Alpha Counting System 10 - 10,000 dpm Alpha Survey Meters 0 - 50,000 counts per minute Beta-Gamma Survey Instruments.05 mR/hr - 200 mR/hr Neutron Survey Instruments

.5 - 5,000 mrem /hr A sufficient number of the instruments, meters and systems listed above shall be maintained operational to adequately conduct our Health Physics program.

Additional instrumentation is maintained for emergency use as outlined in Part I Section 8.

The detectors for the criticality alarm system are calibrated semi-annually and following any repair that affects the accuracy of the measurements.

All other instruments are calibrated semi-annually and following any repair that affects the accuracy of the measurements.

The calibration of the survey instruments shall meet the specifications described in Section 1.11 of Regulatory Guide 8.24, "Health Physics Survey During Enriched License No. SNM-1067, Docket 70-1100 Rev. 7 Date: 1/20/88 Page: I.3-9 l

,~

Committee.

He shall meet the minimum qualifications for a Nuclear Criticality Specialist and shall not be the initial

.. reviewer.

As stated in section 4.1.3, all such approvals shall be recorded in a log maintained under the supervision of the Supervisor, Health Physics & Safety.

4.1.6 Markinc and Labelino of SNM - All mass-limited containers shall be labeled as to enrichment and content.

All geometry limited containers and processes are safe up to the maximum allowable enrichment of 5.0% U235.

4.1.7 Audits 4.1.7.1 Product Develooment - Nuclear criticality safety for all Product Development operations shall be limited to quantities smaller than a minimum critical mass or slab limited storage.

Each such mass limited area shall be isolated from all other fissile material by at least 12 feet.

Criticality control' by any other means shall not be permitted.

Thus, the nuclear criticality safety program in Product Developmtat consists of simple mass or slab limit.

The monthly radiological safety audit of Product Development operations required by Section 2.8 shall I

include verifications to assure that all nuclear I

safety limits are being adhered to.

An annual audit l

1 of l

l License No. SNM-1067, Docket 70-1100 Rev.6 Date: 1/20/88 Page: I.4-3

Product Development shall be conducted in accordance ith the requirements of section 2.8.

.4.1.7.2 Nuclear Fuel Manufacturina Ooerations - Operations at the Nuclear Fuel Manufacturing facility shall be formally audited for nuclear criticality safety as required by the audit schedule in section 2.8.

4.1.8 Trainina and Retrainina - All training and retraining with respect to nuclear criticality safety shall be conducted in accordance with the requirements of section 2.6.

4.2 Technical Reauirements 4.2.1 Preferred Acoroach to Desian - It is the intent of Combustion Engineering to use physical controls and permanently engineered safeguards on processes and equipment in the establishment of nuclear safety limits wherever practical.

Use of administrative controls in the establishment of safety limits will be minimized.

4.2.2 Basic Assumptions and Analytical Methods - Written health and safety restrictions for all operations on radioactive material shall be provided in the form of approved Radiation Work Permits or approved detailed procedures, and appropriate operational limits shall be posted in the vicinity of work stations in both the manufacturing facility and Product Development.

Each operation on fissile material in Building 5 shall be limited to 350 gm U235 for uranium enriched to more than 5.0% U235, and to 740 gms U235 for uranium enriched to 55.0% U235, and Licenst No. SNM-1067, Docket 70-1100 Rev.5 Date: 1/20/88 Page: I.4-4

shall be separated from any other fissile material by 12 feet.

Rods containing sintered U02 pellets enriched to a maximum of 3.0% U235 shall be stored in Building #5.

Slab storage in Building 45 shall be limited to maximum height of 6.0".

A continuous log shall be maintained for each mass limited work station or storage area in Product Development to assure that the limit is maintained and that the enrichment of all material is recorded.

No additional criticality controls are required for Product Development.

Criticality safety of the less complex manufacturing operations is based on the use of limiting parameters which are applied to simple geometries.

Safe Individual Units (SIU) shall be selected from Table 4.2.5.

These units shall be spaced using the surface density method.

The remaining manufacturing operations are evaluated using two dimensional transport and/or 3 dimensional Monte Carlo Codes.

The sixteen group Hansen-Roach cross section library is used for homogeneous systems, while NITAWL and XSDRNPM is used to generate multigroup cross sections for heterogeneous systems.

All calculational methods involving computer codes shall be validated in accordance with the criteria established in Regulatory Guide 3.4, "Nuclear Criticality Safety in

[

l Operations with Fissionable Materials at Fuels and Materials Facilities."

l l

l I

1 I

l License No. SNM-1067, Docket 70-1100 Rev.4 Date: 1/20/88 Page: I.4-5 l

i

Optimum conditions (limiting case) of water moderation and heterogeneity credible for the system shall be determined in all calculations.

The analytical method (s) used for criticality safety analysis and the source of validation for the method (s) shall be specified.

Safety margins.for individual units and arrays shall be based on accident conditions such as flooding, multiple batching, and fire.

The method of deriving applicable multiplication factors shall be specified.

License No. SNM-1067, Docket 70-1100 Rev.4 Date: 1/20/88 Page: I.4-7

t

• 4.2.4 A Moderation Control For moderation control a maximum K of 0.95 shall apply for eff validated computer calculations.

The 0.95 K value shall be eff reduced 0y (1) the applicable 2 sigma statistical uncertainty associated with Monte Carlo calculations and (2) the applicable uncertainties and bias associated with the bench marked calculations.

The basic assumptions used in establishing safe parameters for single units and arrays shall be as follows:

Nuclear safety shall be independent of the degree of moderation between units up to the maxixum credible mist density of 0.1% H O) 2 (0.001 gm H 0/cc) as demonstrated in Sections 7.2.1 and 8.7.

2 Criteria used in the choice of fire protection in areas of potential criticality accidents (when moderators are present) shall be justified in writing.

An audit of the existing fires sprinkler system in the building 17/21 complex shall be conducted once a quarter (Sprinkler Heads, Risers, Distribution Lines, and Pumps) to see to it that it has not been modified or added to in any way that l

l would impair its performance or have an effect on calculated mist l

density.

All proposed changes to the fire sprinkler system, that I

l could affect the building 17/21 complex, will be reviewed and approved by the Manager of Nuclear Licening for their effect on mist density, before such changes are implemented.

Plastic bags which are placed around the fuel assembly shall be left open at the bottom at all times including the period in which the assembly is in storage or which the assembly is being shipped to the reactor site.

Combustible materials in the area shall be minimized at all times.

License No. SNM-1067, Docket 70-1100 Rev.1 Date: 1/20/88 Page: I.4-7A l

i

4.2.5 Limits for Safe Individual Units (SIU's)

Table 4.2.5 Tvoe of Limit Maximum Limit Mass (in 5 gallon or less 35.0 kg's UO2 <5.0% U235 container)

Pellet Shoo Slab (Powder / Pellet) 4.0" Maximum Height.

Slab (Hexagonally stacked rods) 6.0" Maximum Height.

Cold Shoo Slab (Hexagonally stacked rods) 6.0" Maximum Height.

l l

l I

I l

f-i License No. SNM-1067, Docket 70-1100 Rev.3 Date: 1/20/88 Page: I.4-8

4.2.6 Interaction Criteria - Activities involving SNM may be conducted in single or two level areas of the facility.

The surface density method shall be used to evaluate arrays.

All mass units shall have a separation of at least one foot, edge to edge.

Spacing for mass unit activities carried out in the single level portions of the facility shall be such that the contained UO2 and moderator, if "smeared" over the allowed spacing areas would not exceed 50% of the critical water-reflected infinite slab surface density assuming optimum water moderation for minimum mass per unit area.

Slabs specified in Table 4.2.5 require no additional spacing, and may border the spacing boundary of any other array unit.

Portions of the facility contain two levels, each of which may be used for SNM.

In all cases, the floor deck of the second level consists of a 3/8" steel plate (minimum), which is at least 10 ft. above the ground floor.

Mass limits on each level shall be spaced such that the contained UO2 and moderator, if "smeared" over the allowed spacing areas would not exceed 25% of the critical water-reflected infinite slab surface density assuming optimum water moderation for minimum mass per unit area.

License No. SNM-1067, Docket 70-1100 Rev.3 Date: 1/20/88 Page: I.4-9

All array calculations have been performed assuming a doubly infinite planar system, based on the consideration that components of subcritical infinite arrays can be combined where the unit size and cell spacing is preserved.

Array reflection consists of a 16" concrete floor, and a 4" thick concrete roof 25 feet above the floor.

Table 4.2.6 The spacing requirement for mass SIU's specified in Table 4.2.5 is shown below.

Spacing areas shall be established to provide equal distances from the edges of the units to the spacing boundary in all directions.

Limit Spacina Areas Mass 3.5 ft2 Justification for this spacing criteria is provided in Part II of this application.

Whenever more than one mass SIU is allowed in any given hood or box, positive spacing fixtures shall be used to assure spacing.

Carts, limited to one mass SIU shall measure at least three feet on a side, and shall be designed to assure that the SIU is centered.

In cases where the spacing area extends beyond the equipment boundaries, such as the storage facilities, the spacing boundary License No. SNM-1067, Docket 70-1100 Rev.3 Date: 1/20/88 Page: I.4-10

8.12, "Criticality Accident Alarm System" shall be maintained in Product Development areas and the manufacturing facility.

She detectors operate in the range of 1-10,000 mR/hr.

The locations of the detectors within the manufacturing facility are shown in Figure 4.2.1 and within the laboratories in Figure 4.2.2.

The radiation intensity is shown on a central panel located in the Health Physics office for the manufacturing facility (Bldg. #17), and in the main hallway in Bldg. #5 of Produat Development.

There is an alarm which serves as a local and general audible radiation evacuation alarm.

When the alarm is sounded, the Emergency Plan is immediately put into effect.

The monitors are connected to the emergency power system, which is supplied to all emergency lights and alarms in the event of a general power failure within the facility.

This electrical system renders the alarm system operative at all times.

Operation is further enhanced by visual observation by Health Physics personnel.

Alarm operational tests of the radiation monitors are performed monthly by Health Physics personnel.

A radioactive source is used to perform these tests.

The entire system is calibrated semi-annually and following any repair that affects the accuracy of the measurement.

l 4.3 Specific Criticality Safety Criteria i

Specific criticality safety criteria in addition to the general criteria described in Section 4.2 are necessary to assure nuclear safety for l

l several process operations, as described below:

l l

l License No. SNM-1067, Docket 70-1100 Rev. 5 Date: 1/20/88 Page: I.4-12 1

4.3.1 All incoming UO2 powder shall be stored in 9.75" diameter x 11" long stainless steel cans. All powder shall be sampled before being placed in the virgin powder storage area to demonstrate on a 95/95 confidence level that the moisture content of powder lots is less than 5.0 wt.%.

In addition, all damaged packages where containment is breached shall be sampled.

The area in and around the virgin powder storage area shall be kept free of combustibles.

4.3.2 The fire door on the virgin powder prep storage area shall close automatically on activation of the fire alarm and upon electrical power failure.

The automatic closing feature of the door on the virgin powder storage area shall be verified quarterly and records of its performance shall be maintained.

• 4.3.3 A maximum of three 9.75" diameter x 11" long stainless steel powder containers and one 5 gallon powder container or two 9.75" diameter x 11" long stainless steel powder container and two 5 gallon powder containers shall be. allowed in the batch make-up hood in the position shown in Figure 8.2.

4.3.4 The one 5-gallon pail in the Batch Make Up Hood shall be limited to l

35 Kg UO2 and shall be sealed with a water tight cover prior to being stored on the conveyor.

• 4.3.5 The blender hoods shall be restricted to 35 Kg UO2 per station, i

• 4.3.6 The wiper blade, powder plenum, and the drying belt at the Powder l

l l

Preparation Station shall be inspected once per week to assure that the wiper b;ade is functioning properly and that no fuel is l

accumulating in the plenum below the belt.

The depth of the powder l

on the drying belt should be less than 1/2" thick.

The drying belt l

shall be completely enclosed.

The powder accumulation under the drying belt shall be less than 1/2" License lio. SNH-1067, Docket 70-1100 Rev. 4 Date: 1/20/88 P,a g e : I.4-13 l'

l

average.

Records of these inspections shall be maintained.

4.3.7 In the Concrete Block Storage Area, A maximum of 35.0 Kgs 4102 may be contained in 5-gallon or smaller containers.

Each storage position shall be limited to one container.

4.3.8 002 thickness on each of the Pellet Storage Shelves shall be 4.0" or less.

The shelves shall be covered from above by a sheet metal top.

4.3.9 Storage of sintered pellets shall be limited to a 4.0" inch slab limit.

4.3.10 Touching clad rods in horizontal storage shall be close packed in a hexagonal lattice and shall be limited to a 6.0 inch slab.

4.3.11 A maximum of 32 fuel rods shall be allowed in each autoclave.

4.3.12 The boxes on the Double Shelf Rod Storage Racks shall be covered with a tight fitting aluminum cover which overlaps the outside edge of the box by a minimum of one inch.

Fuel rods shall be close packed in a hexagonal lattice and shall be limited to a 6.0 inch slab within the individual rod boxes.

One box may 1

i l

l l

l License lic. S!1M-10 67, Docket 70-1100 Rev. 5 Date: 1/20/88 Paget I.4-14

remain uncovered for short periods of time to allow for the addition or removal of rods for inspection purposes provided that personnel are in attendance.

Boxes shall be a' minimum of E inches edge-to-edge both vertically and horizontally.

The center-to-center distance between adjacent racks shall be at least 55 inches.

4.3.13 In the Fuel Rod Storage Rack fuel rods shall be close packed in a hexagonal lattice and shall be limited to a 6 inch slab within the individual rod boxes.

The entire storage array is covered by a fire resistant roof to assure the exclusion of sprinkler water.

Large signs are posted over the storage array that say "Do Not Use Fire Hoses in this Area."

4.3.14 Fuel assemblies shall be stored only in positions described in Drawing NFM-E-4229.

The assemblies in the storage positions only shall be wrapped with polyethylene with the bottom ends open to assure drainage.

Fire fighting in the assembly storage room with fire hoses is prohibited.

4.3.15 Shipping containers, each containing 2 fuel assemblies, shall be stored outdoors in arrays up to three high.

Containers shall be stored on pavement or blacktop within an 8 foot high chain link fence.

4.3.16 Waste drums shall be stored in designated areas of the pellet shop or on a concrete pad contiguous to the south wall of the Bldg. #21 warehouse.

Packages on the pad will be stored up to two high and contain less than 350 grams U235 each.

Maximum residence time for packages stored on the pad shall be twelve months.

4.3.17 Incoming virgin powder shall be stored in the Bldg. #21 warehouse or in the truck unloading area in the northwest corner of Building 17 it. their original shipping containers only.

License No. SNM-1067, Docket 70-1100 Rev. 5 Date: 1/20/88 Page: I.4-15 e

The size of the array of the containers shall be in accordance with the requirements specified in the NRC Certificate of fompliance and all DOT regulations.

4.3.18 Incoming drums of pellets shall be stored either within the pellet transport vehicle or inside Buildings 17 or 21.

If stored within the transport vehicle said vehicle shall be inside the Buildings 17/21 security fence.

Incoming drums of pellets shall be stored in their original shipping containers only.

Two containers are strapped to a pallet as required by the NRC Certificate of Compliance.

The pallets may be stored anywhere in building #17 or Building #21 with no additional spacing required beyond their physical dimension which is greater than 40" x 40".

The containers are received in a horizontal position.

This condition will be maintained in Buildings #17 and #21.

4.3.19 The size of any array of shipping containers, with the excep-tion of the 927A and 927C Fuel Bundle Shipping containers, shall be limited to a total transport index of 80.

Shipping container arrays shall be separated from one another by at t

l least 20 feet.

This does not apply to 927A and 927C Fuel l

l Bundle Shipping Containers.

However, 927A and 927C Fuel Bundle Shipping Containers shall be separated from all other types of shipping containers by at least 20 feet.

i l

l License No. SNM-1067, Docket 70-1100 Rev. 5 Date: 1/20/88 Page: I.4-16 l

This Page Intentionally Left Blank l

l l

1 l

1 l

l l

l l

l l

{

l License rio, sim-1067, Docket 70-1100 Rev. 1 Date: 1/20/88 Page: I.4-19 L

area in Building #5.

Product Development maintains equipment for mechanical testing, X-ray diffraction, vacuum and inert atmosphere heat treating, radiography, powder processing, and ceramics processing.

1.1.4 Information Known to ADolicant Recardina Foreion Control There is no information known to Combustion Engineering, Inc.

f any control exercised over it by any alien, foreign cc poration, or foreign government.

The stock of Combustion 2ngineering is traded on the New York Stock Exchange.

According to the stock records of Combustion Engineering maintained by its Transfer Agent, The Chase Manhattan Bank, as of December 31, 1979, there were approximately 26,742 stockholders of record, holding 16,337,119 shares of Combustion capital stock issued and outstanding.

Of this number less than 1 percent of all stockholders gave foreign addresses.

1.1.5 Financial OJalifications Combustion Engineering's 10-K which details its finar.uial position is attached as Appendix B.

1.2 Operatino Obiective and Process - Summary The process at the manufacturing facility begins with receipt of UO2 powder enriched to a maximum of 5.0% U235 from Combustion Engineering's License No. SNM-1067, Docket 70-110 Rev.4 Date: 1/20/88 Page:II.1-6

7.0 NUCLEAR CRITICALITY SAFETJ 7.1 Use of Sutface Density Technicue 7.1.1 Use of Surface Density Criteria of 50% for Mass Limited Units on Sinale Levels Mass limited units having a maximum fraction critical (f) of 0.3 are to be spaced to a maximum array surface density of 50% of the optimum critical surface density based on mass per unit area.

The criteria is supported as follows:

Consider the following infinite planar arrays of units containing moderated UO2 having an enrichment of 5.0%. For these arrays, the following parameters apply:

Material - UO2, 5.0% U235, fully moderated Unit Size - a - 17.955 kg U, 38.548 cm. diam., 0.6 gm U/cc b - 17.995 kg U, 35.023 cm. diam., 0.8 gm U/cc c - 18.094 kg U, 33.612 cm. diam., 0.91 gm U/cc d - 17.994 kg U, 28.402 cm. diam., 1.50 gm U/cc r

These units represent 30% (f=0.3) of the minimum unreflected critical mass of 60 kg at l

optimum moderation (Fig. 1.D.13, UKAEA Handbook).

Allowable Sur-face density - The minimum mass surface density for U(5)02 is calculated to be 10.4 kgU/ square foot (Reference 1).

The safe limit is therefore 5.2 KgU/ square foot.

Spacing Re-l quirement

- 56.87 cm center to center spacing in a square lattice.

Reflection

- Sixteen inch thick concrete reflectors on top and bottom of array, spaced 28.43 cm from the center of the units (a).

1 i

License No. SNM-1067, Docket 70-1100 Rev.3 Date: 1/20/88 Pager II.7-1 l

l

8.0 PROCESS DESCRIPTION AND SAFETY ANALYSES This sectLon contains detailed descriptions of all operations in the Manufacturing Facility (Building #17 and #21).

Sufficient detail is provided to permit an independent verification of the adequacy of the controls for the purpose of assuring safe operations.

Nuclear criticality limits are taken from Table 4.2.5 of Part I.

In certain operations, the intricacies of the equipment require further analysis, which is provided herein.

Details of specific calculations used to support various aspects of this analysis, and several statements and considerations in Section 4 of Part I are discussed in this section.

This section provides typical analyses for operations conducted within the scope of this license.

Present arrangements of the equipment in the pelletizing facility are shown in Figure B-1.

(Drawing No.

NFM-J-4077).

This arrangement may be changed in accordance with the procedures in Section 4 of Part I of this license.

8.1 002 Powder Processina 8.1.1 Receiot of Material All UO2 powder is received in licensed shipping containers l

from C-E's dry process oxide conversion plant at Hematite, Missouri.

The as-received 9.75" diameter stainless steel l

l UO2 powder cans, to be stored in the virgin powder storage area (Figure 8.1) and shall be sampled before being placed in the storage area to demonstrate on a 95/95 confidence t

level that the moisture content of powder lots is less than i

5.0 wtt.

In addition, all damaged packages where containment is breached License No. SNM-1067, Docket 70-1100 Rev. 3 Date: 1/20/88 Page:

II.8-1 l

will be sampled.

8.1.2 Sircin Powder Storace Area The virgin powder storage area is isolated from the remainder of the plant on all sides by concrete block walls, a double steel roof, and a metal fire door.

This door is normally in the open position, and is automatically closed upon activation of the fire alarm, and on failure of electrical power.

The automatic closing feature of this door shall be verified quarterly and records of its performance shall be maintained.

These engineered safety features are considered adequate to prevent the introduction of water in the event of a fire.

This area will be kept free of combustibles, and located such that there are no potentially hazardous items such as boilers in the vicinity of the area.

An ammonia cracker is housed in a concrete block building which is located some 25 feet northwest of Building #17.

In view of its many redundant safety features, it is not viewed as a potentially hazardous item.

Criticality Safety Analyses The following assumptions were incorporated into the calculational model of the Virgin Powder Storage Area:

1)

All steel structural materials were neglected.

2)

The fuel was assumed to be a homogeneous mixture of UO2 containing 5.0 wtt H20.

l 3)

All storage positions were filled and each individual can was assumed to contain 35.0 kg's of UO at 5.0 wtt l

2 l

U235.

4)

No interspersed water moderation was considered.

l l

License No. SNM-1067, Docket 70-1100 Rev.3 Date: 1/20/88 Page:

II.8-2 l

The KENO-IV Code with sixteen group Hansen-Roach cross sections was used to determine the reactivity of the Virgin Powder Storage Area under the condition noted above.

Dimensional details of the model are provided in Figure 8.1.

A Keff of 0.7781 0.0043 was obtained for an infinite system in the horizontal direction.

8.1.3 Batch Make-Up Powder containers are removed from the virgin powder storage area and placed on a conveyor for transfer to the Batch Make-Up Hood.

Two 9.75 inch diameter x 11 inch long stainless steel powder containers shall be placed on fixtures in the left side of hood and either a powder container or a 5 gallon pail on the right side of the hood when an appropriate batch of less than 35 Kg U02 is weighed out and put into a 5-gallon pail.

The batch weight and enrichment are recorded on the container.

A water tight cover is secured to these batch containers and they are then conveyed to a lift for transfer to the blender hoods.

The batch make-up operation is enclosed in a ventilated hood.

Sufficient negative pressure is provided to assure a minimum face velocity of 100 fpm.

Criticality Safety Analysis The following conservative assumptions were incorporated in the calculational model of the Batch Make-up Hood and Conveyor Change j

Lift areas:

1.

All steel structural materials were neglected.

l 2.

An external mist of.001 g/cc was assumed.

l 3.

The stainless steel powder make-up cans (9.75" diameter and 11" long) on the conveyor were modelled as a single cylinder in the horizontal direction based on the can containing a License No. SNM-1067, Docket 70-1100 Rev.3 Date: 1/20/88 Page:

II.8-3 l

homogeneous mixture of 35 kg U02 at 5.0 wt % U235 and 5 wt %

E20.

This mixture was assumed to be uniformly distributed within the can.

4.

Two stainless steel powder cans and two 5 gallon stainless steel buckets (10.75" diameter and 14.25" high) in the batch make-up hood were assumed to each contain a homogeneous mixture of 35 kg UO2 at 5.0 wt t U235 with maximum moderation.

The batch make-up hood was assumed to be covered with a 0.25" film of water.

5.

The 5-gallon stainless steel buckets on the conveyors and in the cone change hood and hopper lifts are assumed to contain a homogeneous mixture of 35 kg UO2 at 5.0 wt % U235 and 5 wt

% H20.

This mixture was assumed to be uniformly distributed within the can.

It has been assumed that there is no distance between buckets on the conveyors.

A single 5-gallon bucket of UO2 has been assumed in each hopper lift area and three 5-gallon buckets of UO2 have been assumed in the cone change hood.

All 5-gallon buckets in the cone change hood, the vertical conveyor, and in the hopper lift areas are assumed to be covered with a 0.25" film of water.

The KENO-IV code with sixteen group Hansen-Roach cross sections was used to determine reactivity of the Batch Make-up and Conveyor Change Lift areas under the conditions noted above.

A Keff of 0.7940 1 0053 was obtained for an infinite system in the x and y directions.

Dimensional details of the calculational model are shown in Figure 8.2.

License No. SNM-1067, Docket 70-1100 Rev.0 Date: 1/20/88 Page:

II.8-3A

8.1.4 Powder Preparation and Blendino 002 powder from one sealed batch container (moderation control assured) is transferred to a blender where it is mixed with a binder.

Two separate blenders feed a common powder spread funnel by a means of individual powder transfer pipes entering at a 45 degree angle.

An identical powder preparation line runs parallel to this one at a centerline distance of 13 feet.

The blending operation is enclosed in a ventilated hood.

i License No. SNM-1067, Docket 70-1100 Rev.3 Date: 1/20/88 Page II.8-4 t

Sufficient negative pressure is provided to assure a minimum lace velocity of 100 fpm.

8.1.4.1 Drvino Agglomerated UO2 powder is spread onto the dryer belt from the powder spread funnel to a controlled depth of 1/2".

A complete enclosure is provided around the dryer belt assembly and this enclosure is maintained at a slight negative pressure. The discharge end of the dryer belt utilizes a wiper blade to prevent the flow of significant amounts of material to the plenum under the belt.

Nevertheless, the wiper blade and plenum shall be inspected ence per seek to assure that the wiper blade is functioning properly and that fuel is not accumulating in the plenum below the belt.

Record; of these inspections are maintained.

The belt dryer operates on a 1/2" slab limit.

(The criticality safety analysis also assumed an accidental accumulation of up to 1/2" of powder under the dryer belt in the event of 2alfunction of the wiper blade).

The safety of the i

dryer assembly is assured by this restricted slab thickness.

The grantilator controls are wired to the motor control such that the dryer belt cannot be activated unless the granulator is turned on.

An over i

l temperature condition will shut off the heating elements and light a warning light.

l l

l License No. SNM-1067, Docket 70-1100 Rev.4 Date: 1/20/88 Page:

II.8-5 l

l w~

8.1.4.2 Granulation Dried oxide is gravity-fed into a grsnulator where it is sized for subsequent pressing.

The granulated powder is Ahen gr'.v.:y-fed through a discharge funnel ending in a 2 inch square opening.

A short adapter of 2 inch circular cross section is welded to the funnel to allow connection of a 2" diameter hose wnich is then connected to a portable s

hopper below.

A complete enclosure is provided around the granulator screening mechanism.

The enclosure contains a level probe which will shut off the drier belt and heaters should the granulator discharge funnel fill with UO2 powder.

It is maintained at a negative pressure to preclude dusting.

Criticality Safety Analysis The powder blending, drying, and granulation stations were divided into two parts for calculationsal purposes.

The back end of the stations included the blenders, the powder transfer pipes leading to the powder spread funnel, and the first 10 feet of the 30" wide dryer belt.

The spread funnel is fixed in pcsttion to restrict the powder discharge from it to a 24" wide and 1/2" deep layer of UO2.

The front end of the station included the last 10 feet of the 30" wide dryer belt, the granulatst, the discharge funnel and hose an5 he large cylindrical press feed hopper.

The following conservative assumptions were incorporated into both calculational models:

1.

An external mist of 0.001 g/cc was assumed.

4 License No. SNM-1067, Docket 70-1100 Rev 4 Date: 1/20/88 Page:

II.8-6

2.

Th9 UO2 powdor w s cssu2 d to hava e d3ncity of 3.5 g/cc at an enrichment of 5.0 wtt U235 and a water content of 15 wt %.

3.

Any structure containing UO2 powder was assumed filled to capacity.

4.

Although the belt dryer is limited to 1/2" of UO2 powder, the model allows for an hccidental accumulation of 1/2" under the dryer belt in the event of malfunction of the wiper blade.

5.

All surfaces of the structures containing U02 powder and the surface of the powder in the blender hood and on the dryer belt were assumed to be covered with a 0.25" film of water.

6.

The concrete floor and ceiling have been accounted for in the models.

7.

An infinite array of stations was analyzed although there are only two parallel stations.

In the analysis of the back end of the stations it was assumed that the blender hoods are restricted to a maximum of 35 kg U02 per station, that this mass of UO2 was located at the base of each blender hood directly above each powder transfer pipe and was hemispherical in shape.

In the analysis of the front end of the stations it was assumed that the large hopper (11"OD x 40"L cylinder) contained the UO2 powder at 5 wt t U235.

Sixteen-group Hansen-Roach cross sections were used in KENO-IV to determine the reactivity of the system.

Based on the conditions described above, the following Keff were obtained.

back end of station Keff = 0.51641 0057 front end of station Keff = 0.8372 1 0061 l

Dimensional details of the calculational model are shown in Figures 8.3 and 8.4.

License No. SNM-1067, Docket 70-1100 Rev.0 Date: 1/20/88 Page:

II.8-6A

This Page Left Intentionally Blank i

I l

i License No. SNM-1067, Docket 70-1100 Rev.3 Date: 1/20/88 Page:

II.8-7

This Page Left Intentionally Blank License t'o.

SilM-1067, Docket 70-3100 Rev.3 Date: 1/20/88 Page:

II.8-8 l

l

This Page Left Intentionally Blank I

i l

i I

License No. St1M-1067, Docket 70-1100 Rev.3 Date: 1/20/88 Page:

II 8-9

8clc5 Press Feed Hooper Criticality Safety Anavlsis Alt. hough only one press feed hopper is permitted in any dealgnated area, an analysis was performed in order to account for the possiblity of one press feed hopper being immediately adjacent to another press feed hopper.

The following conservative assumptions were incorporated into the calculational model:

1.

Althdugh the large press feed hoppers (ll"OD x 40"L cylinders) cannot be used with enrichments above 3.5 wt %

U235, two large hoppers were assumed filled to capacity with UO2 powder with density of 3.5 g/cc at an enrichment of 5.0 wt t U235 and a water content of 5.0 wt 1.

2.

Both hoppers were assumed to be covered with a 0.25" film of water.

3.

An external mist of 0.001 g/cc was assumed.

The concrete floor and ceiling have been accounted for in 4

the models.

Sixteen group Hansen-Roach cross sections were used in KENO-IV to determine the reactivity of the system.

Based on the conditions described above, a Keff = 0.3633 1 0042 was obtained.

8.1.6 Linal Mixina Filled press feed hoppers may be rolled to assure complete blending of the die lubricant.

8.1.7 Pressina i

The filled portable hoppers are transferred to the pelletizing presses and secured to assure their stability and the containment of powder.

Powder is gravity fed to the press, and compacted to License No. SNM-1067, Docket 70-1100 Rev.3 Date: 1/20/88 Page. II.8-10

t grson p:sllets which cro plcesd into furnaca boots.

The boats have a maximum height of 4.0 inches.

Only one boat shall be at each press at any one time.

Each press is provided a spacing area _of at least 20 square feet.

The press is provided with enclosures which assure adequate ventilation at the opening face, and at the junction of the portable hopper with the press.

Air flow rates are sufficient to assure face velocities of at least 100 fpm.

8.1.8 Dewaxino and Sinterino Furnace boats containing green pellets are charged in a single line to a dewaxing furnace, and then to a sintering furnace, where under controlled conditions, the pellets attain the desired properties.

Because the UO2 is in a compacted form, dusting is minimal.

Hydrogen burn-off exhaust is vented from the building, and is filtered and monitored as specified in section 3.2.3 of Part I.

The furnaces and their interconnecting conveyors are slab limited, with pellet heights never exceeding 4.0 inches.

t Stored furnace boats containing sintered pellets are limited to a maximum slab thickness of 4.0 ".

8.1.9 Final Sizino Sintered pellets are transferred to the grinder feed system l

where they are aligned for the grinding operation which is i

carried out under a stream of coolant.

The coolant is i

centrifuged to remove solids, and is recirculated at a uranium j

concentration considerably less than one gm/ liter.

The infeeder, grinder and outfeeder have pellet configurations limited to 4.0" i

slab thicknesses, r

Grinder sludge is removed from the centrifuge and dried in an i

l I

License No. SNM-1067, Docket 70-1100 Rev.3 Dater 1/20/88 Page: I1.8-11 1

l n-

oven.

The dried matorial is subscquently stored in the concrote block storage area awaiting final disposition.

An enclosure is provided around the grinder to preclude the dusting of U02.

The enclesure is. maintained at a negative pressure with respect to the room.

The grinder coolant may collect in a one inch deep sump in the grinder and in a 25 liter sump behind the grinder, as shown in Figure B-1.

Experience has shown that no appreciable sludge accumulates in the grinder sump.

The centrifuge is cleaned periodically as required to permit continued operation.

Nevertheless, Figure B-1 does show spacing for the grinder sump to allow for any UO2 settling which may occur.

Grinder coolant is normally recirculated, but may be disposed of by evaporation, or by discharge to the radiation waste system.

Pellets are transferred to a storage rack or to a low temperature bulk drying i

furnace where any trace amounts of moisture are removed prior to rod loading.

Both are limited to a slab thickness of 4.0".

1 l

l i

i l

I License No. SNM-1067, Docket 70-1100 Rev.3 Cate: 1/20/88 Paget II.8-12 i-l

8.3 Scrap Reevele r

All clean scrap is accumulated for reprocessing and recycle with the feed material.

Scrap may be milled to yield desired particle size best suited for the processing, oxidized and reduced to assure removal of volatile additives and to achieve the desired ceramic properties of the resulting recycle UO2, and blended to assure uniformity.

The following equipment is included in the pellet shop annex:

r a)

Oxidation and reduction furnace b)

Milling equipment c)

Boildown equipment d)

General purpose hood e)

Filter knockdown hood f)

Storage facilities (as shown) g)

Blender h)

Micronizer l

The furnace is similar in its operation to the furnaces previously i

described.

Although the feed and exit zones of the furnace are not I

i ventilated, sufficient reserve ventilation (Approximately 1800 SCFM) exists to provide such ventilation if surveys indicate the need.

The l

remaining operations except blending, are all carried out in hoods with sufficient ventilation to assure a face velocity of 100 fpm.

i These operations are controlled by use of a 35.0 kg mass limit in accordance with Section 4.2.5 with spacing provisions taken from Section 4.2.6 of Part I of the application as shown in Figure B-1.

Positive spacing fixtures are used to assure spacing wherever more than one SIU is allowed in any given hood or box.

A material balance log is maintained at the Milling Hood and Micronizer to provide additional assurance that the criticality limit of a 35.0 kg U02 mass limit will not be exceeded at these locations.

L i

\\

License No. SNM-1067, Docket 70-1100 Rev.3 Date: 1/20/88 Page:

II.8-13 l

l 1,, -. _ _ _ _ _ _ _, _ _. _ _ _ _

8.3 Storace and Transfer 8.3.1 Concrete Block Storace Area A concrete block storage area is provided as shown in Figure B-1.

This storage area is intended for 5 gallon pails containing a a

maximum of 35.0 kg of UO2 and has a maximum height of 7 feet.

The blocks are of solid 10" thick concrete, having a minimum density of 125 lb/ft3.

Mortar is used to join the blocks and to secure the structure to the building wall.

Steel shelves, of at least 16 ga. thickness are built into the structure with a vertical spacing of at least 16 inches.

Each storage postion measures 16" wide x 14" deep, and is lined on three sides with 1/4" thick mild steel.

The criticality safety analycis demonstrates that the spacing boundary can be located 48 inches from the front of the shelves.

Criticality Safety Analysis The following conservative assumptions were incorporated in the calculational model of the Concrete B3ock Storage Areas:

1.

All stael structural materials were neglected.

2.

An external mist of.001 g/cc was assumed.

3.

Each storage position was assumed to be full with a 5-gallon steel bucket containing a homogeneous mixture of 35 kg UO2 at 5.0 wt t U235 and 5 wt t H20.

This mixture was assumed to be uniformly distributed within the bucket.

4.

A 0.25" film of water has been assumed on the exterior steel walls of the shelving, the top of the shelves, and tha exterior of each bucket.

The KENO-IV code with sixteen group Hansen-Roach cross sections was used to determine reactivity of the Concrete Llock Storage Areas under the wonditions noted above.

A Keff of 0.3104 1 0049 was obtained for an infinite system in the horizontal direction.

The cemensional details of the calculational model are shown in Figure 8.5.

P License No. SNM-1067, Docket 70-1100 Rev.3 Date: 1/20/88 Fage:

II.8-14

i 8.3.2 Pellet Storace Shelves Steel shelves are provided for pellet storage.

The shelves are 3 high., They have a width of 30" and are limited to a slab thickness of 4.0".

The slab thickness of 4.0" is assured by limiting the number of fuel pellet trays stacked at any position.

l The entire storage array is covered by a sheet metal top which would prevent significant moderation of the array from discharge of the overhead sprinkler system.

Water firefighting is not permitted in the pellet chop.

Criticality Safety Anavlses The following conservative assumptions were incorporated in the calculational model of the Pellet Storage Area:

1.

All steel structural materials were neglected.

2.

An external mist of.001 g/cc was assumed.

3.

Each of the three storage shelves were assumed to hold a 4" thickness of a homogeneous mixture of 002 at 5 wt % U235 at a density of 5.686 g/cc and water at maximum moderation (volume-weighted based on a UO2 density of 10.96 g/cc).

4.

A 0.25" film of water has been assumed on the top shelf, which is empty and the back wall of the shelving.

5.

The concrete ceiling (4"), floor (16") and the back wall (8" concrete block equivalent to 5" solid concrete) were also t

included, r

The KENO-IV code with sixteen group Hansen-Roach cross sections was used to determine reactivity of the Pellet Scorage Area under the j

conditions noted above.

A Keff of 0.7468 i.or49 was obtained for an infinite system in the horizontal direction.

The UO2 loading of the trays was determined by doing a total of 14 measurements.

The pellets pack to au average density of 5.95 gm UO2 i

per cc (5.24 gm U per cc, with a 2 sigma variation of 0.264).

The 16 group cross sections for the pellets were calculated for 0.3766" diameter rods.

Dimensional details of the calculational model is shown in Figure 8.6.

j License No. SNM-1067, Docket 70-1100 Rev.3 Dr.t e : 1/20/88 Page:

II 8-15

t r

This Page Left Intentionally Blank i

l License tio. SNM-1067, Docket 70-1100 Rev.3 Date: 1/20/88 Page II.8-16

8.3.3 Rod Transfer Plat carts measuring 3' x 13'-1/2" are used for transporting

.up to two steel boxes with inside dimensions of 5-1/2" x 8" r

i a 14'4" long, each containing over 300 fuel rods.

The rods j

are assumed to be in a close packed hexagonal lattice with a maximum water to UO2 volume ratio of 0.48, based on a rod O.D. of 0.44" and a pellet 0.D. of 0.3765".

t r

.i i

f I

l i

I i

\\

License No. SNM-1067, Docket 70-1100 Rev.4 Date: 1/30/88 Page:

II.8-17 t

l, From Figure 1.E.16 of UKAEA Handbook AHSB 1, tho critical infinite slab thickness for 5.0% enrichment is about 8

. inches for this degree of moderation.

Applying the safety 2 factor of 1.2 yields an allowable slab thickness of about 6.7 inches.

Accordingly, the rod transfer cart with two j

5-1/2" deep boxes is safe as long as the rods are not stacked highs; than 6" in each box.

Carts may be placed alongside each other, or will be spaced a minimum of 1 foot from other fissile material.

1 8.3.4 Transfer of Material Material may be transferred on carts which accomr.todate one mass or slab limited SIU, or may be transferred by hand, one SIU at a time.

Carts used for mass limited SIU's shall provide for centering of the unit, and shall measure at least three feet on a side.

Because most spacing areas do not extend beyond the physical boundary of the equipment, spacing between transfer carts and the equipment is of no concern.

In cases where the spacing area extends beyond the equipment boundaries, such extends beyond the equipment boundaries, such as the storage facilities, the spacing boundary will be indicated by a colored line.

The line may be crossed by carts only when they contain no more than one mass or slab limited SIU, and then only to permit an operator to transfer that SIU to an available storage position.

8.4 Pre-Treatment of Low Level Licuid Wastes In order to effect a reduction in the quantities of UO2 released to the License No. SNM-1067, Docket 70-1100 Rev.5 Date: 1/20/88 Page:

II.8-18

retention, tanks in Building #6, low level liquid wastes, consisting primarily_of floor mop water will be pumped into a 10 inch diamter, 11 foot long settling tank with a release line located 18 inches above its lowest point.

The water is then passed through a high efficiency closed loop centrifuge system, sampled to verify acceptable discharge levels, and transferred to the retention tanks in Building #6.

The settling tank is located in the rod loading area, and la shown in figure B-1.

Based on past experience, wash water may contain up to 0.001 uC1/cc

( 0.5 gm U/ liter).

The diameter of the tank (10 inches) is less than the critical, infinite water reflected cylinder diameter of 10.5" at optimum 002 to water concentration as shown in Figure I.D.

11 of UKAEA Handbook, AHSB l.

In addition, the optimum concentration necessary to achieve i

criticality in a 10.5 inch cylinder is between 1500 and 2000 gm U/ liter for 5.0% enriched U02, a factor of 3000 higher than the uranium concentrations observed in the mop water handled.

The volume of the settling tank is 23.2 liters.

The allowable surface density is taken as 25% of the critical infinite slab thickness.

Accordingly, Surface Density = 1.38" or 3.26 liter / square foot.

The required l

spacing area for the tank is therefore 7.11 square feet.

j Sludge and other uranium bearing solids will be collected in volume l

l r

I i

l 1

License No. SNM-1067, Docket 70-1100 Rev.3 Date: 1/20/88 Page:

II.8-19 l

limited SIU's.

This material may be subsequently loaded into trays to a maximumadepth of 4.0", dried in an oven and stored in authorized packages awaiting final disposition.

8.5 Rod Loadina and Assembly Fabrication 8.5.1 Pellet Stackina Pellets from the pellet fabrication facility, or from outside vendors are placed on a table where they are aligned for rod loading.

On the table, the pellet configuration is limited to a 4.0 inch slab thickness.

The UO2 pellets are placed on troughs-before being loaded into rods.

8.5.2 Rod Loadina and Fuel Rod Transoort Carts Pellets are transferred from the stacking troughs into rods.

The loaded rods are placed into carts each of which can hold up to 250 fuel rods in parallel sleeves which are spaced on four rings in'an annular fixture with an I.D. of approximately 10 inches and an O.D. of approximately 22 inches.

Guard rails prevent the carts from coming any closer than three feet center-to-center.

The carts are used in normally dry areas to transfer the rods to operations which include end plug welding, weld deflashing and leak testing.

The welding and deflashing operations are performed on one rod at a time.

The leak testing operation is performed on two rods at a time.

Welded and deflashed rods are immediately returned to the cart after each step is completed.

Finished rods are fluoroscoped and are checked for enrichment with a maximum slab limit of 6.0".

License No. SNM-1067, Docket 70-1100 Rev.3 Datet 1/20/88 Page:

II.8-20

e

• Criticality Safety Analysis The following conservative assumptions were incorporated into the calculational model of the RodLoading and Fuel Rod Transport Carts:

1)

Only the 1/4 iach thick, 8" 0.D.

inner steel cylindrical annulus was accounted for in the model.

All other construction material i

was neglected.

2)

The carts were assumed to be infinite array in the x and z directions.

3)

A mist of.001 g/cc water was assumed for all air spaces.

4)

The fuel rods are contained in 1/2 inch, Sch 40 PVC tubes, each 134 inches long.

There are 250 tubes arranged in 4 concentric rings with an average pitch of 1.303 inches.

The fuel tube region of the cart is thus a cylindrical annulus beginning at 7.445"from the centerline of the cart and extending to a radius of 12.711 inches.

On either side of the fuel tube region, is a weld sample box (4.375" x 4.375") attached to the inner side of the cart.

The weld sample boxes contain a 5x5 array of the PVC tubes which hold empty fuel rods for the purposes of weld sampling only.

A cover of 1/4 inch aluminum with plexiglass i

areas encloses the top, sides, and back of the cart.

In the calculational model it has been assumed that all 250 l

positions in the cylindrical area and all 50 positions in the l

weld sample boxes were occupied by the largest diameter rods (0.3765" O.D. UO2 pellets at 10.061 gm/cc stacked density with a I

(

Zr-4 cladding thickness of.028 inch) at the maximum enrichment l

l of 5.0 wt i H20.

It was also assumed that the fuel rods and the License No. SNM-1067, Docket 70-1100 Rev.4 Date: 1/20/88 Page:

II 8-21

PVC tubes extended the full length of the cart (165 inches).

The moderation effects of the PVC have been included in the analysis, however the absorption effects have been neglected.

A 0.25" film of water has been assumed on the exterior sides of the cover.

The concrete floor'and ceiling have also been modelled.

The NITAWL and XSDRNPM codes were used to obtain 16-group cross j

l sections from the 123-group GAM-THERMOS library for input to KENO-IV.

A reactivity for the Rod Loading and Fuel Rod Transfer Cart, keff =

3 0.873 i.0058, was obtained based on the conditions described.

t Dimensional details of the calculational model are shown in Figure 8.7.

8.5.3 Autoclave Corrosion Test j

Two two autoclaves used for corrosion testing of finished fuel rods are shown in Figure B-1.

The stainless steel tanks are 14.

feet long and have an inside diameter of 14 inches with wall i

thickness of 1.5 inches.

The center line distance between autoclaves is a minimum of 66 inches.

Each l

1 f

i I

l i

t j

License No. SNM-1067, Docket 70-1100 Rev. O Date: 1/20/88 Page:

II.8-21A l

[

autocicvo is limitcd to 32 fuol rods by cdniniotretivo control.

The fuel rods are held by stainless steel fixtures

, consisting of eight plates which are five inches wide and al/8 inch thick.

During operation, the interior of the autoclave could conceivably experience all conditions of water moderation, from completely dry to full density water.

Criticality safety of the autoclaves is based on dimensional comparison with the fuel assembly storage area.

The fuel assemblies have been designed for maximum reactivity and have a keff of less than 0.90 in full density water.

(See Section 8.5.7).

The rod spacing in the fuel assembly is thus the optimum.

If the fuel rods were aligned in the autoclave at this optimum spacing, it would thus take 256 rods to achieve a keff of approximately 0,90.

The maximum number of rods allowed (32) provides a large margin of safety under all conditions of moderation and reflection.

Even with all autoclaves filled, the number of fuel rods present (192) would be less than the number required for one fuel assembly of the 16 x 16 type.

8.5.4 Fuel Rod Storace Area The multi-level storage area shown in Figure 8-8 for boxes of fuel rods consists of up to 10 tiers of 32 locations each.

The steel fuel rod boxes have a maximum length of 14'-4" and an inside width and depth of 8 inches and 5-3/8 inches, respectively.

A vertical spacing of 12-1/2 inches between boxes is maintained, the first tier being 18 inches above the concrete floor.

Lateral spacing is restricted by physical barriers to a minimum of 4 inches.

The rod boxes rest cn rest on roller conveyers tn License No. SNM-1067, Docket 70-1100 Rev.4 Date: 1/20/88 Page:

II.8-22

fccilitoto covcsont in cnd out of tho storcgo errcy and cro held in place by a fixed brace.

.The entire storage array is covered by a sheet metal roof to

_ assure the exclusion of sprinkler water.

The fire resistant roof has a 31 pitch to assure adequate drainage to the floor. Water accumulation in the vicinity of the storage rack is not considered credible in view of the close proximity of an open equipment pit in the floor which is 30 feet x 60 feet x 18 feet deep.

A 3 foot deep sump at the bottom of the pit is equipped with a level detector which activates a pump to transfer any accumulated water to the industrial sewer system.

Criticality Safety Analysis The following conservative assumptions were incorporated in the calculational model of the Fuel Rod Storage Area (Figure 8.21):

I 1)

Each of the rod boxes was assumed to contain the smallest diameter fuel rods (0.382") at an enrichment of 5.0 wt t U235 with a density of 10.061 g/cc.

The fuel rods were assumed to be tightly packed in an hexagonal array.

The 8" wide box was filled to a height of 6.25" containing 371 fuel rods.

The fuel was assumed to be dry.

The fuel and clad were homogenized over the volume of the box.

2)

A vertical spacing of 11.5" between rod boxes was assumed.

3)

A lateral separation distance of 3.5 inches between rod boxes was assumed.

Interspersed moderation was not considered credible since moderation control is l

assured.

l l

T I

License No. SNM-1067, Docket 70-1100 Rev.3 Date: 1/20/88 Page:

II.8-23 i

4)

All stool construction m torial was ncglocted.

5)

The concrete ceiling (4") and floor (16") have been l

included in the calculation.

The NITAWL and XSDRNPM codes were used to obtain 16-group

-2 cross sections from the 123-group GAM-THERMOS library for input to KENO-IV, the code which was used to determine reactivity of.the Fuel Rod Storage Area under the conditionr, noted above.

A keff = 0.6850 1 0032, was obtained for a system with four tiers in the vertical direction and infinite array of boxes in the horizontal direction.

License No. SNM-1067, Docket 70-1100 Rev. O Date: 1/20/88 Page:

II.8-23A

8.5.5 Double Shelf Rod Storace Racks The double shelf storage racks for fuel rods hold a maximum of 12 steel, boxes identical in all respects to those in the multi-tier array described above.

Each box is equipped with a tight fitting aluminum cover which overlaps the outside edge of the box by a minimum of one inch.

One box may remain uncovered for short periods of time to allow for the addition or removal of rods for inspection purposes provided that personnel are in attendance.

Spacing between boxes in both a vertical and horizontal direction is a minimum of 6 inches.

Minimum center-to-center spacing f

between storage racks is 55 inches and the racks are considered i

to be present in an infinite array in the horizontal plane.

The location of these racks is shown as in Figure B-1.

Criticality Safety Arsivses t

The following conservative assumptions were incorporated in the calculational model of the Double Shelf Rod Storage Racks (Figure 8.9):

1.

Each of the steel boxes was assumed to contain the smallest diameter fuel rods (0.382") at an enrichment of 5.0 wt t U235 with density of 10.061 g/cc.

The fuel rods were assumed to be tightly packed in an hexagonal array.

The 8" wide box was filled to a height of 6.25" containing 371 fuel rods.

The fuel was assumed to be dry.

The fuel and clad were homogenized over the volume of the box.

2.

The 0.125" pad at the bottom of the box was modelled as water.

3.

All structural materials were neglected.

4.

An external mist of 0.001 g/cc was assumed.

t License No. SNM-1067, Docket 70-1100 Rev.4 Date: 1/20/88 Page!

II.8-24

5.

A 0.25" fila of Wator hcs bocn assuned on tha covor and sides of the box and on the supports on either side of the

. box, which were conservatively assumed to extend the full alongth of the box.

6.

The concrete ceiling (4") and floor (16") have been included in the calculation.

3 The NITAWL and XSDRNPM codes were used to obtain 16-group cross sections from the 123-group GAM-THERMOS library for input to KEND-IV, the code which was used to determine reactivity of the Double Shelf Rod Storage Racks under the conditions noted above.

A keff = 0.9144 1 0065, was obtained for an infinite system in the horizontal plane.

i 8.5.6 Fuel Assembly Fabrication Fuel rods are loaded into the assembly skeleton in a fixture which provides a lubricating water spray.

These fixtures are designed to assure that water cannot be retained.

The Keff for an isolated assemably is less than 0.90.

See Figure 8.10 for all Dimensions of the Fuel assembly.

i i

.i License No. SNM-1067, Docket 70-1100 Rev.4 Date: 1/20/88 Paget II.8-25

8.507 In-Plant Storace of Fuel Assemblies Fuel assemblies are stored in a vertical position using i

. racks of adequate strength to preclude loss of the design i

(

-spacing.

The assemblies in the storage positions only shall

[

be wrapped with polyethylene with the bottom ends open to assure free drainage.

There are 440 storage positions and an adjacent inspection area consisting of 16 positions.

f Within the same room, (but at greater separation distances) there are two horizontal loading tables where the fuel rods are initially loaded into the assembly skeletons, a vertical wash tank where the assemblies receive a final demineralized water rinse, two fixed vertical inspection stands equipped with elevator platforms to allow final Q.C. dimensional checks, and a marked floor area where the assemblies are loaded into shipping containers prior to outdoor storage.

Each of these stations is physically limited to one fuel j

assembly except the shipping container which holds two.

The assembly storage room can thus contain a maximum of 465 fuel assemblies, 440 storage positions, plus 25 additional locations.

All assemblies outside of shipping cor. tainers shall be stored vertically within the design spacing criteria of the Assembl/ Storage Room shown on Drawing NFM-E-4229.

(Figure 8.11).

I Licence No. SNM-1067, Decket 70-1100 Rev.3 Date: 1/20/88 Page:

II.8-26 r

v=_

1)

A 20 x 34_arrcy of csc :blisc was concorvstivoly modeled at a 9.75 inch center-to-center spacing of fuel assemblies within the double rows. The actual average minimum center to center distance within the fuel storage racks is 10 inches.

The distance between rows of fuel assemblies within any given double rack is 35 inches center-to-center while the aisle between the double racks J-37 inches (center-to-center).

This calculational array effectively brings the 25 additional assemblies closer together and provides greater interaction with the 440 assemblies in the storage area than is actually possible.

The calculational array thus contains 680 assemblies while the maximum number in the room is limited to 465.

(See Appendix B-1, drawing No. NFM-E-4229, "Criticality Model Fuel Assembly Storage Room."

By squaring off the racks and totaling the number of fuel assemblies the number 680 is arrived at).

2)

All steel construction material was neglected.

3)

The water mist density has been calculated to be 0.000075 grams per cubic centimeter (see section 8.7).

For conservatism a water-mist density of 0.001 grams per cubic centimeter was assumed to be in and around the fuel assemblies in the storage array. (This is a

! actor of about 13 times higher than the mist density calculated in section 8.7 or atout 17 times higher than the mist density calculated in Appendix D for a single sprinkler head at maximum flow and pressure). A uniform License No. SNM-1067, Docket 70-1100 Rev.4 Date: 1/20/88 Page:

II.8-27

WSter fila thickncss of 0.025 millicatoro w s assum:d on ths fuel assembly surface.

The' actual calculated film thickness

,with a 15% uncertainty was 0.094 millimeters (see Section 8.8).

This calculated film thickness is for 50 degrees F 7

water, while the minimum ambient temperature is actually higher.

4)

One hundred twenty three (123) DLC-16 energy group cross sections were used to calculate the reactivity for an infinite fuel storage array using KENO.

The 123 group was collapsed to 16 groups using XSDRNPM and the reactivity calculated for-an infinite f uel storage array.

The resultant reactivities for 4.1 wt t U235 Fuel were 1.00158 1 0.00608 and 1.00074 1 0.00569 for the 123 and 16 groups, respectively.

Since the reactivities are essentially the same within the statistical uncertainty of KENO the 5.0 wt %

U235 finite fuel storage array was done using 16 energy groups.

5)

The 16 energy group cross sections were generated using XSDRNPM for the 8" concrete walls, 16 inch concrete floor, 4 inch concrete ceiling and the external water mist between the fuel assembly array and the ceilings and the walls.

The 16 group cross section sets described above were then used in KENO-IV to determine the reactivity of the fuel assembly storage area under the above noted conditions for the most reactive assemblies (the 16 x 16 type with the grids being neglected).

Dimensional details of the calculational model and the fuel results obtained are shown in Figures 8.24 and 8.25.

sicense No. SNM-1067, Docket 70-1100 Rev.4 Date: 1/20/88 Page:

II.8-28

Tho rcculting Koff for tho finito fuol ctortga orrey ic 0.842 1 0.004 which is well below a Keff of 0.95.

Using the

,same methodology additional cases were analyzed for a fuel enrichment of 4.1 wt % U235 where the fuel assembly center r

to center spacing and the water film thickness were varied to determine the effect on reactivity.

A tabulation of Assembly Spacing / Mist Density / Film Thick-ness / Reactivity Values follows:

Assembly Mist Film Reactivity for a g/c Scacing Density Thickness Finite Arrav 9.75" 0.001 gms/cc 0

0.69575 1 0.00397 9.75" 0.001 gms/cc 0.0094 cm 0.732 1 0.004 (see note 1) 9.75" 0.001 gms/cc 0.025 cm 0.77224 1 0.00349 9.75" 0.001 gms/cc 0.055 cm 0.89932 1 0.00341 10" 0.001 gms/cc 0

0.69913 1 0.00422 10" 0.001 gms/cc 0.055 cm 0.904562 1 0.00367 A validation of the methodology used to calculate the reactivity values noted is contained in Appendix C.

The local fire departments have been instructed to use only dry chemical extinguishing methods in the fuel assembly storage room NOTE 1:

This is an interpolated value License No. SNM-1067, Docket 70-1100 Rev.1 Date: 1/20/88 Page:

II.8-28A

cnd tha pellot chop.

Signo rectricting fire fighting in this area to dry chemical methods only have been posted at

.each entrance to the assembly storage room.

There is only one vehicle access gate to the fuel fabrication facility.

Thus, criticality safety is assured under all credible conditions of moderation.

8.5.8 Shiocino Container Storace Shipping containers (Models 927Al and 927C1), each containing two fuel assemblies, are stored outdoors in arrays up to three high.

The width and length will vary; thus, the quantity of containers is limited only by the width and length of the space allocated for storage.

The steel shipping container, approximately 3 feet in diameter and up to 217" long, houses two fuel bundles of the types previously described in this license.

The two bundles in each container are separated by six inches.

An eight foot high chainlink fence encloses the storage area.

Criticality Safety Analysis The following conservative assumptions were incorporated into the calculational model of the Shipping Container Storage Area:

1)

The fuel assemblies are assumed to be made of 5.0 wt.1 U235 enriched U02 with no poison shims.

The most reactive assemblies (the 16 x 16 design) were used, i

t 2)

The three high double infinite array of shipping container was analyzed.

3)

The containers were assumed to be flooded and the array was reflected by 12" of water or the top and bottom of the array.

f License No. SNM-1067, Docket 70-1100 Rev.3 Date: 1/20/88 Page:

II.8-29 l

i i

^

+----v w.,, - - - -, -, - _., - - _..

_~

Tho NITAWL and XSDRNPM codes woro uced to obtain 16-group cross sections from the 123 group GAM-THERMOS library for

. input to KENO-IV, the code which was used to determine Teactivity of the Shipping Container Storage Area under the conditions noted above.

A keff = 0.9245 1 0057 was obtained for the system peak reactivity of the system.

The density of water within and exterior to the containers was made identical.

Details of the calculational model are shown in figure 8.12.

This analysis also provides the basis for considering an open or closed assembly shipping container as an SIU which requires no spacing beyond the physical boundaries of the container.

Accordingly, individual containers may be stored in the facility in unrestricted numbers.

8.5.9 Fuel Salvace Off specification fuel rods are cut open and placed into a fixture to facilitate the removal of UO2 pellets. The recovered pellets are sorted to segregate scrap from reusable material.

Ventilation is provided, and the operations are monitored in accordance with Section 15.

This operation is considered a mass limited SIU, with limits taken from Table 4.2.5.

License No. SNM-1067, Docket 70-1100 Rev.3 Date: 1/20/88 Page II.8-30

)

8.5.10 In-Process Storace of Fuel Pellets in Containers Incoming drums of pellets shall be stored in their original containers only.

Two containers are strapped to each pallet, one pallet high as required by the NRC certification of compliance.

The pallets may be stored anywhere in Buildings #17 or #21 with no additional spacing required beyond their physical dimension which is greater than 40" x 40".

The containers are received in a horizontal position.

This condition will be maintained in Buildings #17 and #21.

The size of any array shall be limited to a total Transport Index of 80.

All arrays shall be separated from each other by at least 20 feet.

8.5.11 Buckets containino 35.0ko UO; The UO2 powder and UO2 pellets may be stored in 5 gallon or less enclosed buckets.

Normally the powder and pellets will be dry.

The only time the buckets will be open will be in hoods, which will limit the amount of water that can be introduced in the bucket from the fire sprinklers.

Criticality Safety Analysis A very conservative analysis was done for the following array of buckets filled with UO2 powder.

The conditions, assumptions, and results are as follows:

1)

The steel cylindrical container has an effective inner diameter of 10.75" and an effective height of 14.25".

A 2x2x2 array of containers was analyzed with the buckets in the array seperated by 1 foot.

License No. SNM-1067, Docket 70-1100 Rev.3 Date: 1/20/88 Page:

II.8-31

2)

Each container was filled with 35.0 kg 00 enriched at 2

5.0 wt t U235 and water.

The UO was assumed to have a 2

density of 10.96 g/cc.

The water was assumed to fill the space not occupied by the UO forming a mixture.

2 3)

The KENO-IV code with sixteen group Hansen-Roach cross sections was used to determine the reactivity at the array of 8 containers.

The K,gg for the full water density within the array is 0.91011 1 0.01013.

The K,ff for an external mist of 0.001 gm/cc is 0.76685 1 0.00495.

The following analysis was done for a bucket filled with 0.4" diameter pellets.

1)

Sentered pellets, when randomly loaded pack to an average density of 5.95 gm/cc, with a one sigma variation of 0.264 as determined from a series of 14 measurements.

Thus, at a 95% confidence level, the VH 0/VUO ratio does not exceed 1.0 and from Fig 1 E.1 2

2 of UKAEA Hand book AHSB1, the critical mass for 5.0 wt-

% U235 at the VH20/VUO of 1.0 is in excess of 200 kg 2

Uranium.

8.5.12 Slab Limits for Pellets The following analysis was done for a slab filled with G.4" diameter pellets.

Pellets, when randomly loaded, pack to an average density of 5.95 gm/ce, with a one sigma variation of 0.264, as determined License No. SNM-1067, Docket 70-1100 Rev. O Date: 1/20/88 Page: II.8-31A

d

,from a series of 14 measurements.

Thus, at a 95% confidence

. level,-the Volume of 0 to volume at UO ratio does not 2

2 i

exceed 1.0 and from Fig. l'.E.16 of UKAEA Handbook ASHB1, the critical slab thickness is.6.2 inches.

Dividing by the safety margin of 1.2 results in a slab thickness of 4.8 inches.

8.5.13 Fuel rod Pre ctackino Station Criticality Safety Analysis The following conservative assumptions were incorporated in i

the calculational model of the Fuel Rod Pre-Stacking Station.

1.

The three trays on the positioner table are stacked i

vertically with a distance of 8.5" between the bottom

[

of one tray and the bottom of the next.

Each tray was assumed to contain the largest diameter fuel rods (0.44"OD) at an enrichment of 5.0 wt t U235.

The fuel rods were assumed to be tightly packed in an hexagonal array.

The trays were assumed to be 9" wide and filled t

to a height of 6.1" containing 312 fuel rods each.

l Each tray was flooded with water.

The fuel, clad, and t

water were homogenized over the volume of the box.

[

i 2.

All structural materials were neglected.

3.

An external mist of 0.001 g/cc was assumed.

4.

The concrete ceiling (4") and floor (16") have been 1

included in the calculation.

6 License No. SNM-1067, Docket 70-1100 Rev.0 Date: 1/20/88 Page:

II.8-31B

i f

i

.The NITAWL and XSDRNPM codes were used to obtain 16-group cross sections f rom the 123-group GAM-THERMOS library for input to KENO-IV, the code which was used to determine reactivity of the Fuel Rod Pre-Stacking Station under the conditions noted above.

A keff = 0.d475 1 0054, was obtained for an infinite array of systems 21.0" center-to-center in the horizontal direction.

8.6 Hiah Enriched Uranium Up to 350 gms U235 of <20% enriched uranium compounds may be all Building #17 and #21 for purposeslof evaluation, analysis, or waste management which consists of scanning drums in preparation for their burial.

Such material will be transforred, controlled, and accounted for in accordance with currently approved nuclear material control plans, 'and except for the drums, all material will be placed in discrete locations specifically designated and posted for this material.

None of these materials will be processed through manufacturing operations in Building #17 and #21.

License No. SNM-1067, Docket 70-1100 Rev.0 Date: 1/20/88 Page:

II.8-31C

I 6

,Q M.,....

~

s

.. :h r

~

g 3 9 z

~~'

~~'

wc k

//

g h,

A a

'h h- -' 5 h I

y g

l 3R j

o

~

=

c..

-)

)

ei

$.u..,l E

y

,5,.

f "1

Em vi 3

g

/

g g'

a

~

e

~

- r --

g y

3 I hg](fl r--

.n h,

.inj1

]g, ;

1

j

_ jl l.

1

,l l

,5 Y l p

li t

i l

f r

l 3

l is

,l i

i I

E bl

?

i e

r y

Date:

1/20/88

$' g=

g License No. SNM-1067 t

Docket 70-1100 Rev. 3 Page:

11.8 32

---,n T

Z fg 1

hkk Y $ Y Y

~ 'O

'M QUO vim /NPOWDER QWVEYOR

~2 POLY BUCKET 9.75 x ll LOVG Il @ x ISHIGH 48 5,o y7 3, y.235

=

8ATOI NAKEUP HOOD 5.0 WT 7 H O GiR 2

VUO-HgO

$~g 2

& f m

w x

p

- 12 4

]

il s

4 4

2 7

h <,

gg-p CONECHANGE

??

HOOD es D1 if d

l' sg

'o lL<3 I;>-6

\\r 02

'(]1

~

• 24 -

'7VP

<3 h

k/ I 11 Cf.'. ' *"*

CRITICAUTY LAYOUT i

a

__ m,

36 a

=g,

Lift L//T

,_. E,_.

NFM S81570 00 u n u m. m

r-This Page Intentionally Left Blank License lio. S!1M-1067 Date:

1/20/88 Docket 70-1100 Tsev. 3 Page:

II 8-34

This Page Intentionally Left Blank License tio. S11M-1067 Date:

1/20/88 Docket 70-1100 Rev. 3 Page:

11.8-35

i y

z

=.

~.

h

-Jn ~

l I

w

,i n

~.

B.

t l

a I

o I

a

'k c

l o

l l

l l

J A

u g

4 B> !

i m

M e

c

{

m-ga

/

f 2

R 3 et p.l s/

L

+'? {*m

.s5 r-ll y..

I, d..l s,

c.

o,

?

l F

3

/

j

=

r G

I!

?

6 M

l!

N' l a.

['

m p

y g, '- ' "

g,-

g 13

[;g..

• +'

i

,N e i.

s si ri li,(-

R"M:

n

5 I

1 1

1[ 1 a

E' Fr{ M dgjf i _

t' i

si

$, i p' g)r i

e.

7 g

I l,.

P.

G --*"

~

1 + -

u.

X a

gt I,

i g

- za

~g 2 r *,

g, E

~ vO 3,9 yE h li g

o

,g n.

D 3

mm p

e 3#

L

'o

-y g

6 License No. SNM-1067 Date:

1/20/88

!, '2

L j

4 2

e Docket 70-1100 Rev. 3 Page:

!!.8-35 i

3 m

n o

m m-o z

I

This Page Intentionally Left Blank License No. Smi-1067 Date:

1/20/88 Docket 70-1100 Rev. 3 Page:

II.8-37

)

i This Page Intentionally Left Blank License 110. st1M-1067 Date:

1/20/88 Docket 70-1100 g,

3 Page 11.8-38

This Page Intentionally Left Blank License tio. S!1M-1067 Date:

1/20/88 Docket 70-1100 hev. 3 Page:

II.8-39 l

P

• • • e e

I j

t.

• l\\

E c

E t V

i 7k '

f

3. s.

i

~

I o /y' a

o,

- %g 5%

iT!

Sil.N[ L N

p w;

!!i J l.,iX 5

'4 y

il

.p,-

11

'll i

~-

n 8

K

{ g'. t,

=

8. - ~

.1 oo fL g

g, l

s.

a y

_-v

--9 l

~%

/ff f

}

Q

~g^

T o

.f,j

/ Y._ 1. T '%V[

~

i h

U.,m i

m F. v.

c

8. 5.

75 c

.p

~c r

Iv C

. C.,

~

. - g-

!r

=

~<[

e

- =1

[,.

Zg

n g

_2 3

=

g

.e g5i k

2 l.'

!( n

'b II l$

l5!!

illl liii t

i i l.i ok i i

(~l-Il 1

1 2et r

I 3 A

'. q; l

,s, 8

7 b

l s

• I p

it ii o

t,M

• f s

s l

s

--J jIj g

g l,

?

License No. SilM-1067 Date:

1/20/88 occu.t 70-iion a.v. 3,,

ii.e.,o

a w

u

.. ~ _

6 This Page Intentionally Lett Blank License 110. St1M-1067 Date:

1/20/88 Docket 70-1100 Rev. 3 Page II.8-41

This Page Intentionally Left Blank License tio. Stim-1067 Date:

1/20/88 Docket 70-1100 Rev. 3 Page:

II.8-42

..e e

I

~

n I

f f

v tl iAl r

i 1

1 8

a s.

l t

fl N

4 m.

ll [ l-9

-l4 l"6 t

g 8

t d

4 p.

d lj q

-i 2

f-[4~

4 i

~

=

11' E'

y ;

n i

k I t l

A

'g 3

R"

_p

-4 lI I'I

/

j

-e

'b 6

t n

:...

e,g gM l

j t

=

m

>r n

E e,

1. :1.'.

t

[

=.

r-l 1

This Page Intentionally Left Blank l

i i

I

)

l i

l 1

I t

i f

License No. Stim-1067 Date:

1/20/88 Docket 70-1100 Rev. 3 Page:

II.8-50 I

i I

f

e u

• • • =-%--

y

!I e

i1.e G

4 'i l !,

i 1

7 f l2'2:

3:,

o l,:i-l

.?.

2 llll:l'.

-1 LG-8* II : a6ed t

E

'^a8 00tt-OL 2apou 88/02/1 :ste0 L90t-WNS *0N esuaan j'l '

(;,i

.hj,

,ilM,ij :

I

....,l.,j.

jji li

.I

, r '.

a.

{1. p, 9'

1

.n.--

i g

l e

,4 ; c g !', i ' a ::,

s e.

9 l

!, q i... e{

s I

't

'C g(( ifi 1

(

l B

5 I!sg..;-

I\\

(

l li i j lvi n!i

!i

\\

i s

e b-T

<l

(;.:. 8 s

O 5.,=. ~o" w

!a p,l}

i i

T@ f f

i

/i l.-

! sc i' m

a i

C l

e m

Le tg

'j e,., ;

o'..

Yi l-I f

)

l2

'E

I 4

ji E

- I.,

E gj 1-l I",

y,

)

(

I

=_ :en t__

+t o.m y

s g

8

• i T

I

_.s--A F--A T

! }

- -t a

s 0

]:: ]:: ]:z l

8 4

7._

h.

g' I

l

,l

~

__ _.4 A **

• .o l

1 esp

2 e

w w

o i

g g

g o

m g

29-8*I1 :80ed E 'Aay 0011-04 181300 d

? t; i

80/02/1 :ageG 490t-WNS 'oK asuaan g

=

e

. g n.

1 l

I f l 3

i m

9 es i

G W

g5 2

g 2

I l

f o

l e

1 1 j

I 5:>I 5

0; t

=

i 2

to.

1 i

,e n

e

,0

• Ij [!t-0 s

9 :

d

-No i

i

.s n

Ls,

< t..

G z i

.b W

I 4 e e*

g y i a w 4 1

.

• g o M I. E 8

[. !

e B IE g.I e r, o

e g g e

i :!

. c l e..- !;icI 5

?

! =3 j i =i.

b

_K-I !. 3.15' r

i g

r m

iA B

g y,jg

g. p; u

l.ig e'

I I l

' i ti l I

o I!

M e

,~

R c

~

a.

8 hb il o=

g 4

+

~,# ~

~

C g

g

• J 4--

8, l

d p

l

\\

g

,o a Q

'o L'

a a

e c

w Q

a v

v a v

a-t m_

5 o w w*

a d

2

~

=

l 5 c 7

'o S

~~

e

_.-i g

I u

4 l

V

• b a:

=

a i

O

.. ei.

d;.

0

'g I

E I, W l

%l

~

l l

e l

This Page Intentionally Left Blank License lio. S11M-1067 Date:

1/20/88 Docket 70-1100 Rev. 4 Page:

II.8-53 I

Y Wmg W

R

=

=@

E y

k-g N. g*

N W If m %9'- O )

CDMCasTt Ecas g

L-b6N 3,-

{

l m

Cmd 90( CmA v 1

ats M m

T 7

U U*U U

75 5

5 U~U+E~5 UIU U~E 4

v3 d.

u a

u a

a a

u a

u a

a o

a a

a 5

I f

y 7

E e

39 M

M

' d 4

M h

h bb w

[

U cIsaLLam 3*th -

U 1

~~ ~ ~

.F lu1

l 1

v ;

w w

w v

v

~

i l

)

\\ l +;l\\

Klv 1

i li t

t.'

i-y l+\\

e i

+

V

• }s,

b

'e lj i

! l,

=

1,. c l-

M 2W l

[1 t

& R$

J ti O g_

h' N I

l 1

j j

l l

l r.

D

-F1--

l 4

j '>

+

M l+

+

+

5 l

N f,

i O - (s*

rr b Tv1' 5 PUCIS

=

s 9

0 0

0 W

i f'

t1 a

a Q "q 64 5

T '

</

W y

+ !

l +

+

! +

i++

+

+

+

/

L srw A

vvp = fugIs/

M $tCE & GACR R.E*4R A D W Gao cad 3

( O.

T S*DdL%E G t em I

F e

M

= -

S 4c --

..- y m

23%]

av 3

8 7

6 5

.- ~

~

(crecult M

H

-s

,,'.i l

1 e

c C D G

C i!!Y 8tEL EMia 4M M

I!Ik m

)N

~

4 statoctu e csump l!$

w s Lt.

ce l[}

F hJ t

l N

lH l j,

!#c

=.

- 3 f7[]Ej + (

L*,

b I

M _ f as strom '

A i

-wm

(:

W

'. s

. coatis l

1',.

a E

ass' W 8 *s Y art b D'C" 0 4 g

cl c

I k:

l. -~. ! l u

\\ P E,.H g ' j {"J

=

i

( ' \\ } $ I. )

m-amerinas N 7J r

s D

O

+

+

+

p

}

\\lsi \\i nd Able iI' i

( ' ' ' '

I 1

\\ g rriore y

Q

=

$ WATD MMWsu.lat *( AC 4T G Kl4 LAVEL

• II W D h.

IER c

g s303030006-O I

{wnA E WZO $

l r1GURE B.f4 RT E

L PCE N SE M1 SU M - tO(o7, 8'

OOCK.ET 'O 1100 REV. S MTE -20" B B

_ :- ? " '., ; ~ -'

~~~~.,~ W $=7' :

S M2 h _'

4l M

,'3' i 2.'.'.i.'.00 ?'f.

4e I wt

-i-t.2 :C2.M C 'Y '

\\

~

~ 5mm wm A

t,.=w re r-c

=

nxLA m h_Y E

T a..,

.w. re 7 o

N#

O'. Teens "pe =5

~ "r e-c. wrr9 CE l

%r - _L

~

w

w. 4- -,

a l

1 J

4 2

~

1 3

4

~ ~ - -

=.

_ -m s

r w

m O

E E

-p S-$

=

u g

-- q

s,-o>

r i em s.;

. - m.ccx m i

e i

A f

f 5'CDMC1tETt Ecury i

t 4(>

wwsms a -

4 i,, w.

-no i

• *. - l, Cas 9DE cmAv 1

8ts M W l

3 M

6M+06 Br5 5M 5

5+n 5

DF-n Fri 3

v3 u

a a

a a

a o

a a

n a

a a

a a

b l

T

~

[1.

-m u

u

~

r 7,=. y t

t t

t' s;!

t t

t t

l u

li W

~ " ' ~ ~

1 t

1 i

t t

's

• ! k'

"}5

(*\\

k V

N\\

( *i i

O D

~

'?

l I

t.

s i

w r.c t

b q:

l:

i, i

a<

g-e ~s i

1 a-

-a e oT n.-

u.

l a

n om, -

ii l

j 3

3

(-

l :

f f

I

d. 4d--

i t

+

+

+

+

i+

+

+

E i

i im*

j l

g j

T 2-i m. um p

i

. ssas eap w

+ !

! +

+

J +

is

+

.+

+

+

V-y m.

/

u sr-A m=put13/

4 -

i F*

soste cs wm ---

i

(

h afMEAD F's Gao CN.ds

' 8' " # 8 8'C

• t*K' e suu cv am h

e

_[-

VH!l5!M :

Ri 3 L

^

}

8 7

6

_S

l (It e

I (cnorit

=l 4'

H P J l

d :

o 8 1

'l[y.

i A

I

-g-L r

4

_dl 3

cun p

= $

o c

ii4 r

a.-

l bk ce us a ll '

'N

~'

\\

l m

i i w

d FR]d + (

N_

JL

+

=

- e

~

- 55 R.0Da ;'

I

_E p

a ca mams l' l W

. marts i

=

,.{ :f aes, mu E

l!c ee.uo.am m og p s'cmcmITEtL%

f i

[.mm. l l

'g1

\\1,1;.Le gT nE B

e-u m

aswnonnf y--

- g}{i) g O

D

\\)so \\ \\ stj a ble i l' l

l

\\ g., r i is ' e-i

=

n

=-

g-um 4 wwTr3 Wmau A a sq ac 4T C160*eI3 41 v11 ~ 13 A4Cht NOR C

1 s803030006- 01 l WFM E-92Z9

{

{

FGM E f!

~

L tcE N S E M1 SNM - 80(o7, B-r-

DOCKET 'PO a 600 REV. 3

~-

E mit J-:20 - 8 8

(.

W m n.m l

.l h-

' _. ?

tL

[*

• 4=CEm'#4t4'EWS?LJI h r.. -vTn.

J w=w-

.._u=:-

c ::::-:-2

-- y cir r<Au ry wxt L A

f g a.s,t- * - = *~

3 me.se7c7 w

RfC L At*dMk.T

' W.TI 7%.r b

'^

NAN 3%

l

""C e r

-i~

w r e. g. 64 ttg 2

~

l TR' i -o' w,

Z _ _4 ___ _ _ _

3_

i 1

J i

_2

Fiaure 8.10 Desian Parameters of Fuel Assemblies Fuel Assembly Fuel Rod Array per Assembly 14 x 14 16 x 16 Total No. Fuel Rod Positions per Assembly 176 236 Fuel Assembly Pitch, in.

8.180 8.116 Fuel Rod Pitch, in.

0.580 0.506 Fuel Rod Clad Material Zr-4 Zr-4 Clad O.D.,

in.

0.440 0.382 Clad Thickness, in.

0.028 0.025 Diametrical Gap, in.

0.0075 0.0070 Active Length, in.

136.7 150.0 Total Length, in.

146.963 101.5 Fuel Pellet Material UO2 UO2 Dish Depth, in.

0.015 0.019 Diameter, in.

0.03765 0.325 Length, in.

0.450 0.390 Density, g/cc/t Theoretical 10.412/95.0 10.41/95.0 Density Stacked, g/cc/% Theoretical 10.03/91.5 10.03/91.5 Spacer Grid Material Zr-4 Zr-4 l

No. per Assembly 8

11 Inconel 1

0.90 0.90 K,gg l

l License No. SNM-1067, Docket 70-1100 Rev.3 Date: 1/20/88 Page:

II.8-55

This Page Intentionally Left Blank I

l License No. SNM-1067 Date:

1/20/88 Docket 70-1100 Rev. 3 Page:

II.8-56

r e

t!

I>a r

"I I LS-8'II 'd'd 1

ooti c4 ung g:

V 88/02/I

""o E 'a8 (801-*5 'a "">n p-i.

}

[>-

hl J

J I

if N'

1), hi,Iii t

.-)'g; 7

re gjl:-

iY l

l !

iL.

I I.

i.

i i

lT'i l

'n

- j li

~

l l

[*

• 1 I

a l'

f 3

5 *[$

i r

j i

f..

a

'i.s L l

i li I

z si.. {l$q.

?

b?

2i '-M

,iU s

e i

4 li}

, i :-

g..__,

i 2

I

,/..

1 j.

I co i

.i

,Ed.

lI.lg'

$.(

~

I f

i 3

. udg.

In

/

1 m,, J

=

e i

't l

,i

[

i l

I l

6 e

e 9

l

\\

e G

J

This Page Intentionally Left Blank i

License llo. SNM-1067 Date:

1/20/88 Docket 70-1100 Rev. 3 Page:

II.8-58

.