ML20207G771
| ML20207G771 | |
| Person / Time | |
|---|---|
| Site: | Framatome ANP Richland |
| Issue date: | 01/31/1999 |
| From: | SIEMENS POWER CORP. (FORMERLY SIEMENS NUCLEAR POWER |
| To: | |
| References | |
| NUDOCS 9903120160 | |
| Download: ML20207G771 (200) | |
Text
.
.c DOCUMENT REVISION INSTRUCTION SHEET PAGE 1 OF 1 Y[-/M8I DOCUMENT NUMBER:
EMF-2 DOCUMENT TITLE:
Siemens Power Corporation - Application for Renewal of Special Nuclear Material License No. SNM-1227 DOCUMENT REVISION:
41 IDENTIFICATION REMOVE INSERT (i.E., SPECIFICATION, DRAWING, PROCEDURE, ETC.)
PAGES(S)
REVISION PAGE(S)
REVISIOh Cover Sheet 40 41 Distribution 40 41
)
Table of Contents 1-vi 40 i-vi 41 Chapter 1 1 1-6 36,37 1-1 & 1-6 41 1-11 1-11 41 Chapter 4 4'20 36 4-20 41 4-31 36 4-31 41 Chapter 5 5-3 36 5-3 41 Chapter 10 10-1 & 10-2 36 10-1 & 10-2 41 10-9-10-32 36 10-9-10-32 41 4
10-35 & 10-36 36 10-35 & 10-36 41 10-72 37 10-72 41 10 10-103 ~
36,37 10-89-10-103 41 10-109 37 10-109 41 10-114a 10-114a 41
[
Chapter 14
$418 36 14-18 41 Chapter 15 15-133-15-139 37 15-133-15-13S 41 4
IF THE SPECIFICATIONS OR PAGES ARE ONLY REMOVED AND NOT *tEPLACED, I
PLACE DASHES IN THE INSERT COLUMNS.
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4 IF THE SPECIFICATIONS OR PAGES ARE ONLY ADDmONS (NO REPLACEMENTS),
PLACE DASHES IN THE REMOVE COLUMNS.
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l EMF-2, Rev. 41 Issue Date:
1 i
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Application for Renewal of
. Special Nuclear Material L: cense No. SNM-1227 (NRC Docket No. 70-1267)
- t i
i January 1999 r--
-,,r y,
e
1 1
L SiernenS Power Corporation - Nuclear Division r
m.2 SPECIAL NUCLEAR MATERIAL LICENSE NO. SNM-1227, NRC DOCKET NO. 70-1257 TABLE OF CONTENTS REv.
41 Pg h
CHAPTER 1 - STANDARD CONDITIONS AND SPECIAL AUTHORIZATIONS l
1.1 Corporate Information............
1-1 l
1.2 S ite Lo ca tion.............................................................
1-1 1.3 License Number and Period of License............................
1-2 1.4 Pos s es sion Limits......................................................
1-2 1.5 Authorized Activities.......-.._..................................
1-2 1
1.6 Exemptions and Special Authorizations.................
1-2 i
,' CHAPTER 2 -ORGANIZATION AND ADMINISTRATION l
2.1 Organizational Responsibilities and Authority............................. 2-1 l
j 2.2 Personnel Education and Experience Requirements.................... 2-11 I
j 2.3 Safety Review Committees............................................... 2-14 i
2.4 Training.................................................................................
2-16 l
2.5 Operating Procedures, Standards and Guides........
........................2-18 l
2.6 Configuration Control and Maintenance / Calibration of Safety Related i
Eq uip men t.......................................................................... 2-1 8 2.7 Intemal Audits and Inspections............................................. 2-19 2.8 investigations and Reporting of Reportable incidents...........
2-21 2.9 R e co rd s............................................................................... 2-2 2 CHAPTER 3 - RADIATION PROTECTION 3.1 Administrative Requirements.,..........................................
3-1 3.2 Technical Requirements....................................................
3-2 AP P E N D IX A.....................................................
3-16
]
CHAPTER 4 - NUCLEAR CRITICALITY S4.:TY 4.1 Administrative Practices..............................................
4-1 i
4.2 Technical Practices.........................................
4-5 I I
i l CHAPTER S - ENVIRONMENTAL PROTECTION 5.1 Efflue nt Control.................................................................
5-1 i
5.2 Environmental Monitoring.....................................
5-5 i
! CHAPTER 6 -SPECIAL PROGRAMS 6.1 Proprietary information...................................................
6-1 i 6.2 Occupational S afety................................................................
6-1 j
)
6.3 Emergency Utilises....................................................
6-2 i
6.4 Radioactive Waste Management.................................
6-2 l j.
6.5 U F. Cylinde rs...........................................................
6-3 l
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t i AMENDMENT APPLCATON DATE:
PAGE NO.:
l January 11,1999 i
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l SPC-ND:3330.947 (R-U07/92)
SiemenS Power Corporation - Nuclear Division eur.2 SPECIAL NUCLEAR MATERIAL LICENSE NO. SNM-1227, NRC DOCKET NO. 70-1257 TABLE OF CONTENTS REv.
41 CHAPTER 7 - DECOMMISSIONING PLAN
^
7.1 Decommissioning Plan...................................................
7-1 7.2 Decommissiening Cost Estimate...........................
7-1 7.3 Decommissioning Funding Plan..............
7-1 CHAPTER 8 - RADIOLOGICAL CONTINGENCY PLAN.............................
8-1 t
! CHAPTER 9 -GENERAL INFORMATION t
1 i
9.1 Corporate information.......................................
9-1 9.2 Financial Qualification......................................................
9-1 9.3 Summary of Operating Objective and Process..........
9-1 9.4 Site De scription.............................................................
9-3 9.5 Location of Buildings On-Site............
9-4 i
0.6 Maps and Plot Plans..
9-4 9.7 License History......................................
9-5 AP P E N D I X A............................................................
9-12 k, CHAPTER 10 -FACILITY DESCRIPTION l
10.1 Pl a 9. La y o ut...........................................................
10-1 10.2 Utilities and Support Systems............................................... 10-12 10.3 Heating, Ventilation, and Air Conditioning (HVAC)................... 10-22 j
10.4 Radioactive Waste Handling.............................................. 10-51 10.5 Fire Prote ction................................................................. 10-64 10.6 Criticality Accident Alarm System.................................
10-67 A P P E N DIX A...........................................................10-115 I CHAPTER 11 -ORGANIZATION AND PERSONNEL i
?.
11.1 Organizational Responsibilities..........
11-1 l
11.2 Functions of Key Personnel....................
11-1 1
l 11.3 Education and Experience of Ke 11-1 Operating Procedures..........y Personnel.....
11.4 11-47 11.5 Tra in i n g.......................................................
11-47 j 11.6 Changes in Facilities and Equipment.
11-48 I
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i AMENDMENT APPLCATON DATE:
PAGE NO.;
January 11,1999 il SPC ND:3330.947 (R-it07/92)
SiemenS Power Corporation - Nuclear Division EMF-2 SPECIAL NUCLEAR MATERIAL LICENSE NO. SNM-1227, NRC DOCKET NO. 70-1257 TABLE OF CONTENTS REv.
41 CHAPTER 12 - RADIATION PROTECTION 12.1 Program..............................................................
12-1 12.2 Posting and Labeling...................
12-1 12.3 Intemal and Extemal Radiation - Personnel Monitoring...
12-1 12.4 Radiation Surveys.......
12-3 12.5 Radiation Safety Training........
12-3 12.6 Reports and Rc. cords..................................................
12-4 12.7 instruments..................................................
12-4 i
12.8 Protective Clothing............... _.........................................,......
12-5 i
12.9 Administrative Control Levels (including Effluent Control).............
12-5 12.10 Respiratory Protection.............................................
12-7 12.11 Occupational Exposure Analysis...............................
12-8
{
12.12 Measures Taken to implement ALARA................................
12-9 12.13 Bioa ssay Program........_.....................................
12-9 12.14 Air Sampling and Intemal Exposure Program........................
12-10 i
12.15 Surface Contamination......
..........................................12-12 APPENDIX A..........
.............................................12-14 APPENDIX B................................................................. 12-81 I
CHAPTER 13 - ENVIRONMENTAL SAFETY - RADIOLOGICAL & NONRADIOLOGICAL i
13.1 Extemal Radiation...........................................................13-1 13.2 G a seous Effluents........................................................
13-1 13.3 Liq uid Effluents.......................................................................
13-1 13.4 Groundwater.....................
13-2 13.5 Field S a m pling.................................................................
13-4 CHAPTER 14 - NUCLEAR CRITICALITY SAFETY i
I 14.1 Administrative Practices............
14-1 14.2 Technk al Practices............................................... 14-35 l
14.3 Refe re r m s.................................
. 14-44
. CHAPTER 15 -PROCESS DESCRIPTION AND SAFETY ANALYS:S I
I i
\\
i 15.1 UO Building..........................
15-1 l
2 15.2 Speciality Fuels (SF) Building....................................................15-113 j
i 15.3 Engineering Laboratory Operations (ELO) Building..................15-130 15.4 Wa rehouses.......................................
....15-145 l
l CHAPTER 16 - ACCIDENT ANALYSES...
16-1 I
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AMENDMENT APPLCATON DATE:
PAGE NO.:
January 11,1999 m
l SPC ND:3330.947 (R-1'ppk
SiemenS Power Corporation - Nuclear Division eup.2 SPECIAL NUCLEAR MATERIAL LICENSE NO. SNM-1227, NRC DOCKET NO. 70-1257 TABLE OF CONTENTS REV.
41 LIST OF TABLES Table Pace l
l l-1.1 Specific Locations of Authorized Activities......
1-7 I l-3.1 Restricted Area Airbome Radioactivity Concentration Action Levels a n d Action s......................................
3-12 l
l-3.2 Radiation Safety Instrument Capabilities......................
3-13 1-3.3 Routine Urinalysis Program Action Levels and Actions...
3-14 l-3.4 Routine Lung-Counting Program Action Levels and Actions.....
3-15 i
I. 4.1 System Criticality Safety Controlled Prameters................
4-16 I
l-4.2 Safety Factors for Homogeneous Single Units..
4-32 l-4.3 Safety Factors for Heterogeneous Single Units...
4-33 l
! l-5.1 Boundary ConcentrMon Action Levels..........
5-7 I
l-5.2 Total Boundary Action Levels...........
5-8 1
l-5.3 Liquid Effluent Action Levels and Actions......
5-9 l l
i l-7.1 Plant Decommissioning Cost Estimate Summary..
7-2 11-9.1 Corporate Informeion..............
9-6 I
l 11-10.1 Ammonia Recovera Major Equipment...
10-68
- 11-1 0. 2 LUR Process Equipment....
10-69 1
l i 11-1 4. 1 Critical Parameters for U Compounds Limited to 5 WT.% Enrichment...
14-8 l
{
11-1 4. 2 Homegeneous & Heterogeneous Minimum Critical & Safe Masses.......
14-9 11-1 4. 3 Expressions for Geometric Buckling in Terms of Actual i
Dimensions & Extrapolation Distances...................................
14-10 l l
11-1 4. 4 Compare 25 Keno Va RSIC Test Cases with SPC HP Work Stations.... 14-14 !
l i
ll-14.5 PNL Critical Experiment Data on Clusters of 4.29 Wi% U23s Enriched U O, Rod s in Water.,..........................................
14-18 11-1 4. 6 PNL Critical Experiment Cases Calculation Results with 16-Group,
)
i 27-Group, 218-Group, and 123-Group Cross-Sections.
14-20
{
i 11-1 4. 7 Properties of 2.46% Enriched UO Fuel Rods......
14-24 2
11-1 4. 8 Certified Chemical Analysis of Bf....................... ~..............
14-24 i
11-1 4. 9 B&W Critical Experiment Cases Calculation Results with 16-Group Cross-Sections...
14-25 l
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i AMENDMENT APPLICA18DN DATE.
PAGE No.-
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January 11,1999 av i
I SPC-ND.3330H7 (R 907S2) u.
SiemenS Power Corporation - Nuclear Division eur.2 SPECIAL NUCLEAR MATERIAL LICENSE NO. SNM-1227, NRC DOCKET NO. 70-1257 i
TABLE OF CONTENTS REV.
41 LIST OF FIGURES Fioure Pace l-2.1 Organization Chart...................................
2-24 l-2.2 Organization Chart - Safety, Security, & Licensin 2-25 Approval and Responsibility Matrix.............g..
l-2.3 2-26 l-5.1 Field Sample Station locations........
5-10 1-5.2 Lagoon Test Well Locations.......................
5-11 I
l 11-9. 1 Organi2.ation Chart................
9-7
, 11 9. 2 Rich!cnd Area and SPC Engineering and Manufacturing Facility.........
9-8 11-9.3 Land Use Within 50-Mile Radius of SPC Site - Recreation......
9-9 11-9. 4 Land Use Within 50-Mile Radius of SPC Site - Agriculture.............
9-10 11-9. 5 Land Use Within 50-Mile Radius of SPC Site - Urban................
9-11 11-1 0. 1 SPC Site General Arrangement........................
10-72 i
11-1 0. 2 Plant Equipment Layout Specialty Fuels Building..
10-73 l 11-10.3 Plant Equipment Layout UO Building.............................
10-74 2
i 11-1 0. 4 Plant Equipment Layout UO, Building......
10-75 ll-10.5 Plant Equipment Layout UO, Building.........................
10-76 11-1 0. 6 Plant Equipment Layout UO Building..............................
10-77 2
11-1 0. 7 Plant Equipment Layout UO, Building..........
10-78 ll-10.8 Plant Equipment Layout UO Building..
10-79 2
ll-10.9 Plant Equipment Layout UO Building.......................
10-80 2
11-10.10 Plant Equipment Layout UO Building........................
10-81 2
11-10.11-Plant Equipment Layout UO Building..............................
10-82 2
Il-10.12 Plant Equipment Layout UO Building................................... 10-83 2
11-10.13 Plant Equipment Layout UO Building............................
10-84 2
11-10.14 Plant Equipment Layout UO Building...............
10-85 2
l 11-10.15 Plant Equipment Layout UO Building.............................
10-86 2
11-10.16 Plant Equipment Layout UO Building.........................
10-87 2
i 11-10.17 Plant Equipment Layout ELO Building..............................
10-88 11-10.18 Horn Rapids Road Site and Arrangement - Fire & Water Supply.....
10-89 Il-10.18a Horn Rapids Road Site and Arrangement - Sanitary Drain..............
10-90 l l
ll-10.19 Simplified Schematic HVAC System - SF Building SWUR Facility....
10-91 l
l 11-10.20 Simplified Schematic HVAC System - SF Building Production Facility.. 10-92 j
ll-10.20a NAF Fumace Facility HVAC System Simplified Schematic..
10-93 11-10.21 Simplified Schematic HVAC System - Original UO Building....
10-94 l
2 ll-10.21a Simplified Schematic HVAC System - Analytical Lab UO Building.
10-95 2
l 11-10.22 Simplified Schematic HVAC System - UO Building Line 2 Conversion j
l 2
i Area...................................
10-96 ;
11-10.23 Simplified Schematic HVAC System - Main (South) Addition........
10-97 i i
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1 AMENDMENT APPUCATION OATE:
PAGE NOJ I'
i January 11,1999 v
i SPC-ND.3330 947 (R-U07/92)
SiemenS Power Corporation - Nuclear Division EM F.2 SPECIAL NUCLEAR MATERIAL LICENSE NO. SNM-1227, NRC DOCKET NO. 70-1257 l
TABLE OF CONTENTS REv.
41 LIST OF FIGURES (Cont.d)
- Fiaure Paae t
i 11-10.24 Simplified Schematic HVAC System - U 0. Facility..
10-98 3
11-10.25 Simplifit.d Schematic HVAC System - ELO Building...........
10-99 11-10.26 Simplified Schematic HVAC System - ELO Building Addition.....
.10-100 i
11-10.27 Simplified Schematic HVAC System - Contaminated Clothing Launay l
Facility............
..10-101 l
i ll-10.27a Simphfied Schematic - SWUR Incinerator Shroud Cooling System...10-102 l
- ll-10.27b Lagoon Uranium Recovery / Solids Processing Facility Ventilation i
System Flow Diagram............................
..10-103 l
11-10.28 Plant Equipment Layout - ARF Building..............
....10-104 11-10.29 Ammonia Recovery Waste Management Facility Engineering Flow Diagram..........
.10-105 l
Il-10.29a Flow Diagram Lagoon SA - Sewer lon Exchange Project...............10-106 l l
11-10.30 Plant Equipment Layout - LUR Facility..
.10-107 11-10.31 Engineering Flow Diagram - LUR Production Facility..
.10-108 j
11-10.32 Fire Alarm System..
............................................. 10.33 SPC Site General Arrangement Dry Conversion First Floor..
..10-110 l 11-10.34 SPC Site General Arrangement Dry Conversion Second Floor.....
..10-111 11-10.35 SPC Site General Arrangement Dry Conversion Third Floor.,..
.10-112 11-10.36 SPC Site General Arrangement Dry Conversion Fourth Floor........10-113 l 11-10.37 Dry Conversion Simplified Air Flow Diagram..........
.10-114 i
l
! 11-1 3. 1 Monitorir.g Well Description..
13-5 l l
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l ll-14.1 PNL Critical Experiment Layout (Reference 6).........
14-17 l i
ll-14.2 B&W Critical Experiment Layout....
14-23 j l
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AMENDMENT APPLCATON DATE:
PAGE NO.:
SPC-ND 3330 947 (R-1/07S2)
EMF-2 Revision 41 l
l Issue Date:
l APPLICATION FOR RENEWAL OF SPECIAL NUCLEAR MATERIAL LICENSE NO. SNM-1227 (NRC DOCKET NO. 70-1257) i Distribution D. L.
Belt B. F.
Bentley (4)
J. B.
Edgar l
B. N.
Femreite
{
R. L.
Feuerbacher J. W. Fredericks S. F.
Gaines i
T. M. Howe W. G.
Keith D. C.
Kilian L. J.
Maas C. D.
Manning-3 C. S.
Powers l
T. C. Probasco A.
Re: araz I.
J.
Urza R. E.
Vaughan C. A. Ward USNRC/ Document Control Desk (6)
USNRC-RIV/W.L. Britz DOH/L. Wainhouse Document Control (5)
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t SiemenS Power Corporation - Nuclear Division eup.2 L
SPECIAL NUCLEAR MATERIAL LICENSE NO. SNM-1227, NRC DOCKET NO. 70-1257 I
i l
}
PART I-LICENSE CONDITIONS
- REV, 1
41 CHAPTER 1 STANDARD CONDITIONS AND SPECIAL AUTHORIZATIONS I
l i
t 1.1 Corporate informatign f
f 1.
t t
The name of the. applicant is Siemens Power Corporation (SPC).
Applicant is !
incorporated in the State of Delaware with its principal corporate offices located at l l
1550108th Avenue N.E., Bellevue, Washington 98009-0777. All of the common i j
stock' of Applicant is owned by Siemens Corporation, a Delaware corporation with !
i headquarters in New York City. Siemens Corporation is, in turn, wholly-owned by !
{
Siemens AG headquartered in Munich, Federal Republic of Germany. The Engineering ;
i and Manufacturing Facility of the Nuclear Division of SPC, for which this application is being made, is located at 2101 Horn Rapids Road, Richland, Washington 99352-
}
{
i i
0130.
i 1.2 Site Location l The Engineering and Manufacturing Facility is located in the state of Washington,
)
county of Benton, city of Richland, it is sited on a 320-acre tract, 0.9 miles west of the intersection of Stevens Drive and Horn Rapids Road within the north boundary of !
the city of Richland. The site is on the south side of Horn Rapids Road which provides access.
All activities with special nuclear materials are conducted within a controlled access [
The processing of uranium compounds is conducted primarily within the UO area.
2 and Specialty Fuels (SF) Buildings with some development activity or pilot scale work i
in the Engineering Laboratory. Liquid waste processing is conducted primarily in the Ammonia Recovery (AR) and Lagoon Uranium Recovery (LUR) facilities which are sited within the waste storage lagoon area. Solid waste is packaged in the various
. facilities and stored in containers in designated storage areas while awaiting shipment
- to a low level radioactive waste disposal site or incineration of the combustible waste in the SF Building. Storage of various uranium compounds is conducted in the various production facilities or in the Radioactive Materials Storage Warehouse, Materials Warehouse, Fuels Storage Warehouse, and the UNH Drum Storage Warehouse.
Storage of UF cylinders is conducted outside on pads at the UF. Receiving and Storage Fecility ir the northeast portion of the site, and packaged fuel elements or other uranium products are stored outside or in a warehouse while awaiting shipment.
I l
AMENDMENT APPLICATION DATE:
PAGE NO.;
I May 29,1998 1-1 SPc-ND 3330 947 (R-UO7'92)
~.
i Siemens Power Corporation - Nuclear Division eup.2 SPECIAL NUCLEAR MATERIAL Ll0ENSE NO. SNM-1227. NRC DOCKET NO. 70-1257 i
PART I-LICENSE CONDITIONS REV.
36 1.3 License Number and Period of License 1.3.1 Special Nuclear Materials License f
I! This application is for renewal of Special Nuclear Material License No. SNM-1227 (NRC Docket No. 70-1257). The current license expires on September 30,1992 and renewalis requested to' cover a period of ten yects from the date of issuance.
I 1.4 Possession Limits i
1.4.1 Uranium-235 t
i
-l 1.
Three hundred fifty grams, in addition to the limits listed below, of any l
enrichment or form for analytical purposes and for sources.
j 2.
Twenty-five thousand kilograms contained in uranium compounds in j any form enriched to a maximum of 5 wt% in the U-235 isotope.
1.4.2 Plutonium (< 500 arams) 1.
One milligram and not more than 1.5 millicuries as contained in sealed sources and standards.
2.
Less than 500 grams as PuO or PuO -UO as stored waste.
2 2
2 i
1.5 Authorized Activities Specific locations of authorized activities involving special nuclear materials are
- identified in Table 1-1.1.
I i
j 1.6 Exemotions and Special Authorizations I
1.6.1 Criticality Accident Alarm System i
j i
Pursuant to 10 CFR 70.24(a), SPC's criticality accident alarm system is not required i.
! ~ to monitor special nuclear material under water in the waste storage lagoons. The ;
criticahty alarm system is described in Section 10.6.
l l
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l j AMENDMENT APPLCATIONDATE:
PAGE NO.:
l I
October 28,1996 1-2 l
SPC ND:3330 947 (R-1/07S2)
1 L
SiemenS Power l Corporation - Nuclear Division me.2 SPECIAL NUCLEAR MATERIAL LICENSE NO. SNM-1227, NRC DOCKET NO. 70-1257 i
l PART I-LICENSE CONDITIONS REV.
41 I
1.6.2 Plutonium Possession and Storace i
Trace ' quantities of plutonium-may enter the plant as contamination in uranium feedstock (UF, scrap pellets / powder, etc.) that contains reprocessed uranium in any amount.~
In addition, SPC currently stores a small amount of plutonium as.a contaminant in drummed solid waste generated during the past decommissioning of an onsite mixed oxide facility.
1.6.2.1 Plutonium Contaminated Feedstock SPC may receive, process, store, and ship reprocessed uranium containing plutonium i
.; and other transuranic isotopes.
1.
a.
The concentration of transuranic isotopes in such uranium shall be l
limited ~ to that specified in ASTM specification C996-90 for r
" Enriched Reprocessed UF."; i.e., the alpha activity for plutonium s
and neptunium (transuranics) shall be less than 3.3 Sq/gU.
i i
b.
The alpha activity of plutonium and neptunium in the uranium for i
the TVA lead assemblies described in SPC's amendment application
}
dated November 13,1998 shall be no greater than 50 Bq/gU.
2.
SPC shall, when it expects to receive such uranium, obtain from the shipper certification that the uranium is within the limits for transuranics i
as specified in either 1.a or 1.b, as applicable.
1.6.2.2 Plutonium Contaminated Waste Storace SPC is presently in possession of plutonium as PuO and PuO -UO left over from past 2
2 2
. decommissioning of an onsite mixed oxide facility. This material is in the form of j
contaminated solid waste stored in drums, i
j l These containers shall be stored in the SF Building, Room 162 autoclave pit in i
accordance with the following controls:
l 1.
These stored containers shall be sealed with gaskets.
2.
.The SF Building storage pit shall be exhausted by the building HVAC system. Two stages of HEPA filtration shall be provided prior to exiting
' the exhaust stack, j
3.
The air exiting the SF Building storage pit shall be continuously monitored. and sampled, and the samples analyzed weekly for i i
l radioactive material content, j
j
~ Assurance of containment shall be verified at least once every six l l
months by visual inspection and smear survey of the stored waste I
- E drums. The inspection and surveys shall be documented. All indications !
l l
of drum leakage shall be investigated and appropriate action taken.
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- . AMENDMENT APPLCATION DATE
PAGE NO.:
. November 13,1998 1-3
{
sPc-ND:3330.947 (R-1/07/92) l
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SiemenS Power Corporation - Nuclear Division EMF-2 SPECIAL NUCLEAR MATERIAL LICENSE NO. SNM-1227, NRC DOCKET NO. 70-1257 a
PART I-LICENSE CONDITIONS REV.
41 4.
In order to provide continued containment, SPC may find it necessary to repackage the containers. These activities shall be performed using a special Radiation Work Procedure (RWP).
5.
All alpha contamination discovered by smear surveys or air sainpling within the pit area shall be considered as plutonium alpha unless proven i
otherwise.
1.6.3 Labelina Exemption i Pursuant to 10 CFR 20.1904(a) requirements, a sign bearing the legend, "Every
. container or vessel in this area, unless otherwise identified, may contain radioactive material," may be posted at entrances to each building in which radioactive materials are used, stored or handled, in lieu of the requirement to have a " Caution, Radioactive Material" or " Danger, Radioactive Material" label affixed to each container of licensed i material.
l 1.6.4 Waste Disposal i
! Pursuant to 10 CFR 20.2002, disposal of solid waste material containing 30 pCi/ gram j
or less to other than a licensed waste disposal facility is authorized. The low enriched I
~
uranium shall not exceed 30 pCi/ gram of dry solid waste material. The uranium shall be essentially uniformly distributed throughout the waste material.
1.6.5 Soecial Nuclear Material Safoouards Specific safeguards requirements for special nuclear material are given in Safeguards i Amendment SG-2 issued pursuant to 10 CFR Parts 70, 73, 74 and 75. Those j
j conditions are not affected by this licensing action.
i l
1.6.5.1 Physical Security f'
j i SPC 'shall follow the special safeguards conditions given in the Safeguards i Amendment SG-2 and the NRC-approved security plan submitted in accordance with j i the provisions of 10 CFR Part 73.67(c)(1).- The NRC-approved security plan is:
i ANF-538(P), " Physical Protection Plan for Material of Low Strategic Significance." This document shall be maintained in a current and approved status and shall be properly implemented.
l I
1.6.5.2 Material Control and Accountina 4
SPC shall follow the special safeguards conditions given in the Safeguards i i
l Amendment SG-2 and the NRC approved Fundamental Nuclear Material Control Plan j l
(FNMC) submitted in accordance with 10 CFR Part 74.31(b). The NRC approved i FNMC Plan is:
l 1
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AMENDMENT APPUCATON DATE:
PAGE NO.:
November 13,1998 1-4 sPc-ND:3330.94R 1/0W92)
=
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SiernenS Power Corporation - Nuclear Division ew.2 SPECIAL NUCLEAR MATERIAL LICENSE NO. SNM 1227, NRC DOCKET NO. 70-1257 -
PART I-LICENSE CONDITIONS REV.
41 EMF-12(P), ' Nuclear Material Safeguards Procedures Description for the Fuels Fabrication Plants."
This document shall be maintained in a current and approved status and shall be properly implemented.
l 1.6.6 Authorization at Reactor Sites l SPC is authorized to possess fuel assemblies or fuel rods at reactor sites for the l purpose of loading them into shipping containers and delivering them to a carrier for transport.
i 1.6.7 Authorized Release Guidelines i
SPC is authorized to release equipment, scrap or jacilities for unrestricted use, or for termination of license according to the " Guidelines for Decontamination of Facilities
'. and Equipment Prior to Release for Unrestricted Use or Termination of Licenses for j
. Byproduct, Source, or Special Nuclear Material" as published by the U.S. Nuclear i
Regulatory Commission dated April 1993.
j l
1.6.8 Authorized Criticality Alarm System Outaae i
l SPC is granted an exemption from 10 CFR 70.24(a) for the purpose of performing i maintenance on the criticality alarm system. Sections of the criticality alarm system may be taken out-of-service provided that all movement or processing of fissile material in affected areas is halted for the duration of the outage. Health and Safety Technicians shall conduct continuous surveys of the areas during the criticality alarm j
syster:. outage.
I 1.6.9 Notification l
i Notifications to the NRC shall be made as required by regulations with the exception i
of 10 CFR 20.2202(a)(2) and (b)(2) as they apply to restricted areas. Reports to the !
j NRC shall be made as required by regulations with the exception of those paragraphs i
in 10 CFR 20.2203 which refer to 10 CFR 20.2202(a)(2) and (b)(2) as they apply to I restricted areas.
l 1
i 1.6.10 Authorized Workplace Air Samplina Adiustments SPC is authorized to adjust Derived Air Concentration (DAC) limits and Annual Limit of Intake (ALI) values in process areas to reflect actual physical characteristics of 7
the airborne uranium.
1.6.11 Authorized Release Guidelines for Hydrofluoric Acid i
SPC is authorized to release hydrofluoric acid manufactured by the dry conversion process for unrestricted commercial use providing the following conditions are met:
1 1.
A representative sample of each batch of hydrofluoric acid product I
shall be obtained and analyzed for uranium; AMENDMENT APPLCATON DATE:
PAGE Noa November 13,1998 1-5 sPC-ND.3330 947 (R-1/07/92)
Siernens Power Corporation - Nuclear Division euF.2
. SPECIAL NUCLEAR MATERIAL LICENSE NO. SNM-1227, NRC DOCKET NO. 70-1257 t
PART I-LICENSE CONDITIONS REV.
41 1.6.10 Authorized WorkDiace Air Samplina Adiustments SPC is authorized to adjust Derived Air Concentration (DAC) limits and Annual Limit of Intake (All) values in process areas to reflect actual physical characteristics of the airborne uranium.
1.6.11 Authorized Release Guidelines for Hydrofluoric Acid l SPC is authorized to release hydrofluoric acid manufactured by the dry conversion j process for unrestricted commercial use providing the following conditions are met:
i i
l 1.
A representative sample of each batch of hydrofluoric acid product shall be obtained and analyzed for uranium;
-l 2.
A batch shall be no larger than 46,000 liters; j
3.
The specific activity of any batch released for unrestricted use shall be s 3 pCi/ml.
I l
l l
1.6.12A_uthorized Release Guidelines for Ammonium Hydroxide SPC is authorized to release ammonium hydroxide produced at the Ammonia I
Recovery Facility for unrestricted commercial use provided the following conditions are met:
i 1.
A representative sample of each batch of ammonium hydroxide i
product shall be obtained an analyzed for uranium; I
l 2.
A batch shall be no larger than 40,000 liters; i
i 3.
The uranium concentration in the ammonium hydroxide shall not i
exceed 0.05 ppm.
l I
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i I
l i
?
.f i
i I
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l AMENDMENT APPUCATON DATE:
PAGE NO.:
December 15.1998 1-6 i
sPC-ND:3330.947 (R-1/07/92)
SiemenS Power Corporation - Nuclear Division eur.2 SPECIAL NUCLEAR MATERIAL LICENSE NO. SNM-1227, NRC DOCKET NO. 70-1257 PARTI LICENSE CONDITIONS
- REV, 41
- 1.
TABLE l-1.1 Specific Locations of Authorized Activities (Cont.d)
Location SNM Authorized Activity Modular Extraction /
Uranium Solid Waste (up to Sorting. shredding, compaction Recovery Facility 5 wt. % U-235) and uranium recovery
'MERF).
t I
I l
l j
i i
I l
t f
1
~
t i
I I
- l 1
1 I
l l
I I
4 i
4
.f l
i I
-t l
t s
f-1 1
I i '
i 4
l t
l l
i l
I 1 AMENDMENT APPLCAT!GN DATE:
PAGE NO.:
l February 6 1998 =
1._11_
SPc-ND.3330.947 (R-UO7'92)
CO CO E
0 --
l m*
oB 5
gm Tatde I-4.1 (Cont'd_)
E-h T-COMPONENT CONTROL TYPE DISCUSSION OF ANY SPECIAL O
Q CONTROLS USED / ADDmONAL O
g
{'
EXPLANATION OF CONTROL TYPE
>O GEO VOL FNA NAA CCU CCM MCU MCM PPC ARA SPA x
2 I
KS I
>V Cyundrical
_; o 2 b'.
m Tanks. Filters "ad 0"*
O yo g
Eg4mnt
.g y
r-3 og 510.02* nominal X
X X
X Favorable geometry control used y
7,
F I D.
alone is limited to homogeneous q
-g solutions / slurries such as UO,F, g7 mC and ADU that have a martmum U ga
,^
density of 5.53 grn/cm*. More g
(n g--
g g
m g3 reactive materials are isolated from these tanks by physical or process Z
z' conditions so that they cannot 0)
QO enter these tanks or credible m
7
[
concentrations of these materials O
CO 5" are less than Br0 g U/hter.
h 3-Z 3
O Controls in addition to geometry q
g are genere!!y used to protect 3
m downstream processes.
z y
Z Cylindrical tanks and filters less than this dimension are also U
j sppropriately spaced to assure i
neutron interactions with acceptable m
e u
xm Failure of geometry control or H
y spacing between Exed pieces of g
p equipment is controlled by design.
O a
w9 Tw en m 8
wM N E s
- 5
?
ro
SS S"
Pi e ECm T
e I
An L
'c s
7' N P IbaI7 U
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i 9
5 3
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,8
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1 Eu 9
9 L
Nc l
7 I
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E Ea N
Nr i
S OD
!,Iy.
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Si ki!Ii O
Ni s l
N Mon D
I 1
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I5 I
N
,7 S
N
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R lq C
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TaNe I-4.1 (Cont'd.)
>mO COMPONENT CONTROL TYPE DISCUSSION OF AtN SPECIAL Ek CONTROLS USED f ADDmONAL
>V EXPLANATION OF CONTROL TYPE
-{ O m
g
_D_ N._.
GEO VOL FNA NAA CCU CCM MCU MCM PPC ARA SPA
>O x' '
1l2 y
r3
-:g x
c-Equipment i
OZ h
Mop sinks X
X X
Barrel tums X
X X
CD CD~
g m su 7m Barrel transfer X
X X
d' h '
(n QQ m
HEPA filters X
HaMon bucket X
X X
X O
Z E-tumbiers Z
gOO O
Panet make up X
X X
X q
tables g
g Weste boxes and X
X X
X Z
N drums CO Z
Outges trays X
X X
X X
s 80 ft' filter X
X X
g g
presses l
O z
O Xm o
i Z
O b
8 6>
u y
O
^
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g h,
b D
~=
-s t
e
SiemenS Power Corporation - Nuclear Division EMF 2 SPEGlAL NUCLEAR MATERIAL LICENSE NO. SNM-1227, NRC DOCKET NO. 70-1257 PART I-LICENSE CONDITIONS REV 36 i
TABLE l-4.2 SAFETY FACTORS FOR HOMOGENEOUS SINGLE UNITS l
Safety Psameter Critical Parameter Safety Factor Safe Mass SNM, M, Critical Mass SNM, M.
O.45 Safe Mass SNM, M,t Critical Mass SNM, M.
0.75 (Exceeding of M,t is excluded by engineerir:g l
controls)
Safe Mass Moderator, Critical Mass of 0.50 l
M,%
Moderator, Ma.
Safe Spherical Volume, V, Critical Spherical Volume, V,s 51 0.75 V, > 51 0.80 Safe infinite Cylinder, D, Critical Infinite Cylinder, 0.85 l
D, Safe infinite Slab, S, Critical Infinite Slab, S, S < 3 cm 0.75 j
S > 3 cm 0.85 l
Safe Concentration, C, Critical Concentration, C, 0.50 l
l l
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AMENDMENT APPLCATON DATE:
PAGE NO.:
Odo%r 28,1996 4-32 l
sPC-ND 3330 947 (R-1/07/92)
SiemenS Power Corporation - Nuclear Division EMF-2 SPECIAL NUCLEAR MATERIAL LICENSE NO. SNM-1227, NRC DOCKET NO. 70-1257 I
i PART I - LICENSE CONCITlGNS REV.
41 specified in 10 CFR 20.1302 as reasonably achievable and in accordance with 10 CFR
! 20.2003. Procedures shali be adequate to assure that the effluent treatment systems function properly, and that immediate steps are taken to rectify any observed j
deficiencies as soon as practicable. See Table I-5.3 for action levels and required i actions regarding liquid effluents.
l i
i Released liquid wastes are combined and discharged to the Richland City lift station l
l where the total combined liquid effluent from the plant is pumped to the Richland Municipal Sewerage System.
The combined liquid effluent shall be continuously sampled and the flow measured at the SPC effluent monitoring station.
The f
composited samples shall be analyzed for uranium and regulated chemicals. Any i increase in the chemical or uranium content of the composited samples statistically l 1
f above those limits described in 10 CFR 20.2003 or the State of Washington Liquid Waste Discharge Permit shall be cause for an investigation and appropriate corrective i
action.
5.1.2.1 Sanitarv Wastes Sanitary wastes shall be discharged to the sanitary sewer system which joins other liquid wastes prior to being discharged to the Richland City lift station.
i 5.1.2.2 Process Coolina Waste Water I
Process cooling water shall be isolated from actual process atmosphere by double physical barriers. Process cooling water shall be discharged from various facilities,
(with the exception of the ELO Building) via building sewer systems separdte from l both sanitary and process chemical waste sewers. Process cooling water may be disposed of by discharge to the municipal sewerage system or discharge to the SPC Process Chemical Waste Lagoon System.
5.1.2.3 Process Chemical / Radioactive Wastes All process radioactive liquid wastes shall be routed to the lagoon system. Some lagoon solutions require further treatment prior to discard to the sewer.
These solutions shall be treated, as necessary, for chemical / radioactivity removal prior to release to the sanitary sewer system.
The release of chemical wastes to the sanitary sewer system is controlled by local authorities via a permit system. The licensee shall notify NRC for informational l
purposes of any occurrences which, by permit, require reporting to the authorities, l
4 l
l i AMENDMENT APPLICAION DATE:
PACE NO :
l April 23,1998 5-3 j
sPc-ND.3330 947 (R-107/92)
Siemens Power Corporation - Nuclear Division I
EMF-2 SPECIAL NUCLEAR MATERIAL LICENSE NO. SNM-1227, NRC DOCKET NO. 70-1257 l
PART I - LICENSE CONDITIONS l REV.
l
{
36 5.1.3 Process Chemical Lanoon Manaoement System l
1.
i i The lagoons shall be sealed on the bottom and all sides with an impervious liner to
~
l prevent the migration of lagoon contents to the adjacent subsurface soil or 3
j groundwater. The liner consists of a double layer of impervious material, separated by
)
a layer of sand or 'other material used to maintain spacing between liners. A system l of sampling tubes shall be installed between the liners to provide sampling capability I
to permit detection of leaks in the upper liner.
Routine monitoring of the integrity of the upper liners shall be accomplished by f l
i
, drawing a vacuum on each group of the "between-liners" sampling heads at least - !
j l monthly, unless weather conditions (e.g. ice and/or snow) make it too hazardous to j l
l
! personnel to perform such sampling. In the event that a cignificant amount of liquid is i pumped from any sampling head (s), the liquid shall be analyzed for fluoride and l
uranium content. If uranium and fluoride are present above previously measured levels, an investigation shall be initiated which shall include:
l l
1.
Additional between-liner sampling; I
i 2.
Lagoon solution sampling for comparison of the content of the sample to that of the lagoon; l
i 3.
Checking the integrity of the lower liner of affected lagoons; for i i
Lagoons 1 and 3 by activating sampling lines located between the.l l
lower liners and the original Petromat liners of these two lagoons; or checking the integrity of the lower liner of Lagoon number 4 by sampling the three dry wells associated with the three " French Drains" located under the lower liner of this lagoon; and 4.
Making use of the lagoon test well system.
l l The between-liner sampling system is the first line of defense for detecting liner leaks, and sampling shall be scheduled monthly. The beneath-the-bottom liner leak detection.
(
system shall be activated at anytime the upper liner is determined to be leaking to confirm the integrity of the lower liner. Test wells are provided around the lagoon I
system as a backup to provide the capability to detect leaks penetrating both liner i
layers.
1 In the event that a leak in an upper liner is confirmed, the liner shall be repaired. A I
report of the leak, including results of the investigation and corrective actions taken, shall be forwarded, in writing, to the Administrator, NRC-Region IV within 90 days of detection of the leak.
l l
l
- AMENDMENT APPLICATON DATE:
PAGE NO.:
October 28,1996 5-4 SPC-ND.3330.9471R 1107/92)
I
l Siemens Power Corporation - Nuclear Division eur.2 SPECIAL NUCLEAR MATERIAL LICENSE NO. SNM-1227, NRC DOCKET NO. 70-1257 PART ll-SAFETY DEMONSTRATION REv.
37 construction (approximately 70 x 172 x 12 ft high) is of concrete block on poured-in-place skirt walls. The inner side of all exterior walls are insulated and covered with fire rated gypsum board. The gypsum panel joints are taped and sealed, and the interior surfaces are suitably painted. The interior partitions throughout the building, used for process
- control, are either concrete block or fire rated gypsum board. The roof is made of eteel l deck plates supported on steel trusses, covered with insulation, and a 20-year, builtup roof 1
j system.
The fire loading of the building is kept to a minimum through monthly inspections described in Paragraph 2.6.4 of Chapter 2 of Part 1.
l I
Fire extinguishers are strategically positioned throughout the building and inspected l
monthly. Fixed / rate-of-rise temperature sensors throughout the building provide fire alarm i
capability.
15.3.1.4 Environmental Safety l
15.3.1.4.1 Containment / Confinement - Material processed in the ELO Building is !
contained or confined in open or closed primary containers for UO or U 0, 2
3 i
powders and UO pellets; tanks for uranyl nitrate (UNH); tubular glass. plastic, i
2 fiberglass or metal columns for various solutions going through solvent l
extraction or ion exchange; hoods for powder and pellets; and fumaces for l
calcining powder and sintering pellets.
The concrete floors in the ELO Building are sealed to be liquid tight and there j i
are no floor drains. Liquid effluents which could contain uranium or other !
hazardous material are treated to reduce such materials to levels within i j
regulatory limits prior to discharge.
15.3.1.4.2 Heatina. Ventilation and Air Conditionina (HVAC)- The ELO Building has l three independent HVAC systems. The north side of the building is basically an office / service area recirculating-type (K26) supply system with an unfiltered exhaust. The southwest portion of the building is a research and l
development area with a combination once-through and recirculation (K24) supply system and a double HEPA filtered exhaust (K25) system. The j southeast portion of the building is made up of engineering test operations, instrument laboratory, metallography laboratories and various chemical laboratories with a once-through (K45) system, double HEPA filtered POG (K56) exhaust system. The north and south sides of the building are isolated l
with a structural wall and access to the south side is gained via an airlock.
)
Simphfied schematic diagrams of these HVAC systems. are shown in Figures 11-10.25 and 26.
j I
AMENDMENT APPLICATION DATE:
PAGE NOJ e
September 4,1997 15-132 SPC-ND.3330 947 (R-1/07/92)
SiemenS Power Corporation - Nuclear Division eup.2 SPECIAL NUCLEAR MATERIAL LICENSE NO. SNM-1227, NRC DOCKET NO. 70-1257 PART 11 - SAFETY DEMONSTRATION REV.
41 15.3.2 Gadolinia Screo Recovery The Gadolinia Scrap Uranium Recovery facility (GSURI is located in the basement of l
the ELO Building.
The function of GSUR is to purify off-speification uranium streams. (solids' and liquids), including streams containing gadolinium oxide (gadolinia). The GSUR pellet dissolver converts UO and/or UO /Gd 0 pellets into 2
2 2 3 uranyl nitrate (UNH) feed for the solvent extraction process. The pellet dissolver is a continuous process which uses hot, concentrated nitric acid to dissolve the pellets, deionized water or recycled UNH to adjust the uranium concentration in the UNH to approximately 200 grams uranium per liter (g U/l) of UNH solution, and finally pumps this solution to the solvent extraction feed tank.
Purification is achieved by solvent extraction (SX). The process for powder is essentially the same I exceptf' ' powder dissolution conducted in batch-mode dissolvers and powder -
f derived LwH is filtered prior to the solvent extraction step. The product from l solvent extraction is a low uranium concentration UNH solution in 55 gallon drums l that is suitable for addition into the nuclear fuel fabrication process.
The main components of the GSUR process are:
j l
For Powder 4
- 1) Dissolver tank and hood;
- 2) Various 9.5 inch ID tanks and filters and mop sinks l
- 3) Mixer / settlers, carbonate wash tank, and drip pans I
- 4) UNH product barrels i
i
- 5) Moderated five gallon storage l
l 1
- 6) Raffinate storage tanks
- 7) The facility scrubber system I
These components are located in Rooms 51 and 53 of the ELO Building.
i 8
For Pellets i
- 1) Vacuum transfer system
- 2) Dissolver and oxidation tanks l
t
- 3) Pump, lag storage and dump tanks
- 4) Boiler i
- 5) Vac-U-Max transfer filter and drip pans These components are located in Roorn 52 of the ELO Building.
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AMENDMENT APPLCATION DATE:
PAGE NO.:
August 26,1998 15-133 i
sPc-ND:3330 947 (R. 907/92)
o l~
Siem' ens Power Corporation - Nuclear Division eur.2
' SPECIAL NUCLEAR MATERIAL LICENSE NO. SNM-1227, NRC DOCKET NO. 70-1257 PART ll-SAFETY DEMONSTRATION REV.
41 1
15.3.2.1 Criticality Safety - Powder 1.
Criticality safety of the equipment included in this process is provided by controlling the uranium mass allowed in the dissolver tank, the geometry of the cy!indrical tanks and slab mixer / settlers, the uranium conccntrations in scrubber solutions and product drums.
Dissolver Tank and Hood l The batch controlled powder dissolver is located in Room 53 and is a starting point l
of the operation. UOx powder is placed in the dissolver where nitric acid is added.
l Usually, any available UNH that requires purification is blended with the dissolved
! uranium oxide at this step. The powder dissolver can also be used to produce I uranyl nitrate with a controlled free nitrate concentration by combining UNH and l nitric acid.
l I
Criticality safety in the dissolver (and hood) is maintained by controlling the mass of the batch operation to 20 kg UO (17 6 kg U) and by limiting the material forms to 2
UOx and UNH. An inventory sheet is maintained at the hood. The only cranium-bearing feed streams to this process are (1) hand addition of UOx oowder and (2) low concentration (s 140 gU/l) UNH from a five gallon tank. The dissolver itself is i
an 18 inch tall by 12.75 inch OD stainless steel tank.
Summarv of Accident Conditions j The dissolver hood is controlled for criticality safety purposes to 20 kgs of U. The I
process is limited to approximately 8 kg per dissolver batch for process reasons.
I i Abnormal conditions include double batching. Double batches (40 kgs - which is l about 5 times the process limit) of 5 wt.% enriched UO powder in the dissolver 2
- tank, fully reflected, will result in a k,,,less than 0.95.
j l
Sensitivity studies show that adding more than 50 kgs of powder with a density near 1.5 g/cc to the dissolver, fully reflected, is needed before unacceptable k,,
values are reached in the dissolver. This is a very large margin considering that a i normal process batch is about 8 kg and that, because of the dissolver offgas (DOG)
! system design (including over flows and drains to other favorable geometry tanks),
fissile solutions cannot be transferred to this tank through the DOG header.
2.5 Inch ID Tanks: Filters and Moo Sinks in Room 53 l
f The cylindrical tanks used in the solvent extraction (SX) process, which include the l
l SX tanks and the supply and metering tanks, are fabricated from 1/8 inch thick AMENDMENT APPLCATON DATE:
PAGE NO.:
l August 26,1998 15-134 sPC-ND:3330.00 (R-1107/92)
I Siemens Power Corporation - Nuclear Division sup.2 SPECIAL NUCLEAR MATERIAL LICENSE NO. SNM-1227, NRC DOCKET NO. 70-1257 PART 11-SAFETY DEMONSTRATION REV.
41 stainless steel. The tank inside diameter is 9% inches. The lengths of there tanks are either 3'3" or 5'6" depending on where they are located. The bottoms of the l
tanks are six inches above the floor.
Three types of UNH recycle filters are used in the process: a sock filter that is 9%
inches in diameter by 34 inches long; a basket filter that is about six inches in diameter and 12 inches long; and several cartridge filters which are two inches in diameter and 20 inches long.
t l A mop sink (filter pan), located in the northeast corner of Room 53, is a four inch deep by 12 inch diameter open topped cylinder welded to a 14 inch long funnel, and t
is used to filter solids from mop and other waste water. A filter sits inside the top i portion of the sink. The overall length is less than 16 inches with a one inch I
i diameter overflow line at the top of the funnel.
i Criticality safety in this equipment is maintained by the safe geometry of the vessels
! and by controlling the enrichment to 5% maximum.
4 Summarv of Accident Conditions System geometry precludes a criticality accident in any of the tanks, filters, or mop i
sinks discussed in this section. The potential accident interfaces with the DOG scrubber are prevented by overflows installed on each vessel that will routinely l contain fissile material and by drain lines on the vessel vent lines to the scrubber.
! Even if solutions were to get into the scrubber, the concentration will be less than l 140 g U/l and would be quickly diluted by the scrubber solution.
l Mixer Settlers, Carbonate Wash Tank, and Drio Pans e
The mixer settlers, carbonate wash tank and drip pans are all slab geometry. The l j carbonate wash slab tank also has a poly-mass that floats on the carbonate to facilitate separation of the organic and carbonate. The mixer settler and carbonate wash tanks are 6.25 inch thick horizontal slab tanks with O.5 inch overflow holes l
centered 4.25 inches above the bottom of the tank.
The drip pan under the i
j dissolver is s 1 inch deep. All other drip pans are s 4.0 inches deep.
Criticality safety in these vessels is maintained by the safe slab thickness for the i
uranium forms allowed. Enrichment is also controlled to 5% maximum.
l Summarv of Accident Conditions l
I i
j i
1 i No conditions leading to unacceptable k,,,, values in these vessels were identified.
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} AMENDMENT APPLCATION DATE:
PAGE NO.:
l August 26,1998 15-135 i
sPC-ND.3330 947 (R-UO7/92)
i
- Siemens Power Corporation - Nuclear Division EM F-2 L
SPECIAL NUCLEAR MATERIAL LICENSE NO. SNM-1227, NRC DOCKET NO. 70-1257 PART ll-SAFETY DEMONSTRATION REV.
l 41 i
UNH Product Barrel Fillina and Storsoe
+
After verifying thet UNH concentration is less than 140 g U/l, it is pumped to 55-gallon barrels and placed in-storage, Criticality safety is maintained by controlling enrichment to 5% maximum and by controlling the uranium concentration in the UNH to a maximum of 140 g U/l (50% of the minimum critical concentration).
l Summarv of Accident Conditions The 55-gallon product barrel is an unfavorable geometry. The conditions that could lead to a criticality accident are:
- 1) Exceeding 289 g U/lin multiple drums stored edge-to-edge;
- 2) Exceeding 450 g U/l UNH in a single drum; and
- 3) Exceeding 300 g U/l UO -H O in a single drum.
2 2 f
L l
' The defenses againct these accidents include:
i
(
-- Before UNH can go critical in a 55-gallon drum (23 inch diameter), the U i
concentration must exceed 450 g U/l. (Minimum critical diameter for 450 g U/l UNH solution is over 25 inches).
The target solvent : extraction feed concentration from the powder 1
. dissolver is 200 g U/l.
I
- The maximum theoretical loading using 100% tri-butyl phosphate (TBP) as l
i the organic is about 435 g U/l.
l The maximum theoretical loading using SPC's Criticality Safety-approved l j
. mixture of 30 volume % TBP and 70 volume % dodecane organic is nominally 130 g U/l. The process make up of TBP-dodecane typically will never extract more than 95 g U/l. If organic in the process is loaded to 130 g U/l, the' solvent extraction process will not work and this will be i
i
- detected by the operator.
I
}
'~
_ The specific gravity of the UNH is measured and confirmed to be within i
l l
established limits before the UNH is transferred to the drum.
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j AMENDMENT APPLICATON DATE:
PAGE NO.:
August 26,1998 15-136 sPc-ND.3330.947 (R-1/07/92)
r SiemenS Power Corporation - Nuclear Division eur.2 SPECIAL NUCLEAR MATERIAL LICENSE NO. SNM-1227, NRC DOCKET NO. 70-1257 PART 11 - SAFETY DEMONSTRATION REV.
41 Moderated 5-aallon Container Storaae and Volume Controlled Oraanic Separator e
Five gallon containers are used to store moderated compounds from the GSUR process.
Criticality safety depends upon controlling the enrichment to 5%
maximum; controlling the mass to one safe batch per container; and maintaining a minimum 12 inch spacing between containers.
Summary of Accident Conditions Overbatching, flooding (between containers), and spacing violations were considered. Should overbatching occur, k,,, is less than 0.95 for an infinite array of i
4 containers on a 23 inch square pitch with a double batched container added in the i center. Overbatching is prevented by requiring an inventory label with net wt. and
! enrichment be affixed to each container. Criticality safety limit cards giving safe i
l batch weights by enrichment are posted at each storage location.
Spacing l
violations are prevented by metal floor grids into which the containers are set. If an f array is flooded, the moderator between containers isolates containers from each other, resulting in k,, being that of the individual container; i.e., 0.698 for a single e
batched container and 0.925 for a double batched container.
l l
l
- Raffinate Storaae Tanks l The raffinate storage tanks in Room 51 are 10-inch Sch. 80 polypropylene pipe with I a lengt; of approximately 15 feet. The ID of these tanks is 9.56 inches. The tank wall is % inch thick polypropylene reinforced with resin rich fiberglass. The tanks i
consist of two banks of four tanks each. These tanks are used to store raffinate l i
until the U concentration of the raffinate is verified to meet the limits imposed on Lagoon 3 (1000 ppm) to which the raffinate is discharged.
i i
The raffinate storage tanks are favorable geometry for UNH with concentration up l 23
- to 1000 g U/l and enrichments up to 6% sU.
Summarv of Accident Conditions l
i I
i The normal concentration of the raffinate is about 150-250 ppm U. Concentrations !
l of up to 5 g U/l would be the result of a major process upset. Hypothetical upset !
conditions such as flooding due to a flow reversal can cause the feed to go to the 1 product state with little extraction.
i Product can also be discharged to the raffinate tank instead of the product tanks if I
. the organic flow to the solvent extraction process is stopped. The raffinate is !
l
! transferred to interim receiver tanks where the contents are checked prior to being l AMENDMENT APPLCATION DATE:
PAGE NO.:
{
August 26,1998 15-137 l
sPc-ND.3330.947 (R-1/07/92) i
n 1
SiemenS Pnwer Corporation - Nuclear Division eur.2 SPECIAL NUCLEAR MATERIAL LICENSE NO. SNM-1227, NRC DOCKET NO. 70-1257 PART ll-SAFETY DEMONSTRATION REV.
41 f transferred to the raffinate storage tanks. All of these tanks are favorable geometry I tanks. No identified process upset could cause the raffinate storage tank contems to approach the 1200 g U/l modeled.
ELO Facility Scrubber System The scrubber system used in the ELO Facility in Room 51 consists of the following components:
- 1) Dissolver offgas (DOG) scrubbcr/ stripper tanks;
- 2) Makeup tank;
,3) Mystaire scrubber: and
- 4) Mystaire scrubber surge tank l
l The DOG receives offgas frcm the powder dissolver, pdlet dissolver, and a mop powder dissolver. This offgas is routed to two favorable geometry packed column scrubbers which scrub NO, from the offgas stream.
A water makeup tank is utilized to maintain the proper amount of water makeup to the system. A continuous bleedoff of scrubbed solution is discharged to the ELO drain system which automatically discharges to Lagoon 3.
i The offgas that exits the DOG scrubbers is routed to the POG portion of the system
! and enters upstream of the Mystaire scrubber. At this point exhaust from the SX slab tanks and product loadout drums is combined with the DOG exhaust and enters l 1 the POG scrubber portion of the system.
The combined exhaust then passes l
through a Mystaire scrubber to remove any residual chemical fumes.
j f
( Summarv of Accident Conditions
- Large quantities of UOx in the scrubber pads and sump or filling the Mvstaire
- scrubber with concentrated UNH solution will both result in unacceptable conditions.
The only method of getting UOx into the scrubber is for it to be entrained in the i
scrubber offgas.
The scrubber design ensures that all offgases that have the l
. potential for entrained UOx powder must be processed through the DOG system before it gets to the POG. It is not credible for significant amounts of UOx to enter :
I the ELO Mystaire scrubber via this route. Also, the pH of the UNH facility Mystaire j i
scrubber solution is typically less than 3-4. Similar operating conditions in the ELO l l
scrubber prevent solid buildup in the ELO Mystaire scrubber.
In addition, the g
Mystaire scrubber operates with minimal liquid hold up in the sump by design.
I Multiple overflows provide control of liquid depth in the sump to safe levels.
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Siemens Power Corporation.- Nuclear Division sup.2
. SPECIAL NUCLEAR MATERIAL LICENSE NO. SNM-1227, NRC DOCKET NO. 70-1257 PART 11-SAFETY DEMONSTRATION REV.
41 i
15.3.2.2 Criticality Safety - Pellets Criticality safety of the equipment included in this process is provided by controlling the mass allowed in 5-gallon buckets, the geometry of the cylindrical tanks, and the form and l
enrichment of uranium compounds in the' pump, lag storage and dump tanks and the l
pellet transfer system.
Vacuum Transfer System The vacuum transfer system, orsrating within a hood, is used to convey small batches l
(approximately 5 kgs at a time) of pellets to a separator and hopper, from which the pellets I
1 are discharged at frequent intervals into the dissolver tank.
i I
l l Criticality safety in the vacuum transfer system is maintained by restricting the form of the
. uranium to 5 wt% enriched UO, pellets. The transfer lines are geometrically safe at 2 I inches in diameter. The separator and hopper are geometrically safe 8.5 inch ID
{
cylinders.
li Summary of Accident Conditions i
The separator and funnel were analyzed with UO at various pellet diameters and volume 2
of water to fuel ratios (VM,) with concrete upper reflection, because the separator is near l
the ceiling, and water reflection on all other sides. The pellet diameters were varied from
~
0.5 inch to 0.1 inch and the range of VM, used was 1.6 to 3.4. The peak reactivity for i
0.10 inch diameter pellets in the separator and funnel occurs at VM,=3.4. The peak k,
{
i (0.931, including 20) occuiTed with 0.2 inch diameter pellets and VM,=3.0. The alalysis j does not include the system's wall material.
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1 * - Dissolver and Oxidation Tanks l
I
~
The pellets delivered to the dissolver tank sink to the bottom, maintaining a " bed" of pellets I
several inches deep in the_dissolver tank. Concentrated nitric acid is continuously pumped l
l into the bottom of the tank. Steam from the boiler is added to the nitric acid to heat it. As i
- the hot acid flows up through the pellet bed, it dissolves the pellets to make a-high-i concentration UNH. The UNH then " overflows" through a pipe tv,ar the top of the dissolver tank and into the oxidation tank. The high-concentration UNH in the oxidation i
tank is mixed continuously. The specific gravity of the UNH is monitored and adjusted to l
meet the solvent extraction (SX) feed requirements of approximately 200 g U/l.
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} AMENDWENT APPLCATONDATE:
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l August 12,1998 15-138a l
SPC-ND.3330.947 (>.;07/92) i
SiemenS Power Corporation - Nuclear 6aiSion eur.2 SPECIAL NUCLEAR MATERIAL LICENSE NO. SNM-1227, NRC DOCKET NO. 70-1257
{
I PART ll-SAFETY DEMONSTRATION nev.
41 Criticality safety in the dissolver and oxidation tanks is maintained by the geometry of the tanks and the form and enrichment of the material in them. The dissolver tank and the j
oxidation tank were modeled as 43 inch long 7 inch diameter cylinders (actual ID=6 inches with the dissolver tank having maximum a height of 43 inches and the oxidation tank,25 inches). The Pyrex glass wall material of the tanks was not included in the model. Since these tanks do not sit on the floor, full water reflection was assumed.
Summarv of Accident Conditions The pellet dissolver and oxidation tanks were analyzed with UO at various pellet 2
i diameters and volume of water to fuel ratios (V,/V,), which is more reactive than UO in nitric acid or UNH. The upper bound on the pellet diameter was 0.5 inch.
2 I Since pellets are dissolved in this equipment and get quite small, the lower bound on pellet diarneter was 0.1 inch. The range of V,/V, used was 1.6 to 3.4. The peak k,,, (0.833, including 20) occurred with O.2 inch diameter pellets and a V,/V, of 3.2.
This model does not include the wall material of the tanks and, because the tanks j do not sit on the floor, full water reflection was assumed.
Pumo. Lao Storaae and Dumo Tanks After dissolution, UNH of the correct uranium concentration (approximately 200 g U/l) for feed to SX is routed through the pump tank, thelag storage tanks, and then the dump tank from which it is fed to the SX in Room 53 of the ELO Building.
Criticality safety in these UNH tanks is maintained by the geometry of the tanks and by controlling the enrichment and form of the materialin them. The tanks have OD's of 9.75 to 10 inches and were modeled with 10 inches of UNH.
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c AMENDMENT APPLCATON DATE:
F AGE NO:
l.
August 12,1998 15-138b SPc-ND.3330.947 (R 1/07/92) l
~ Siemens Power Corporation - Nuclear Division eur.2 SPECIAL NUCLEAR MATERIAL LICENSE NO. SNM-1227, NRC DOCKET NO. 70-1257 PART ll - SAFETY DEMONSTRATION REV.
41 P
Summarv of Accident Conditions Calculations were performed with various concentrations of homogenous UO -H O 2 2 mixtures taking credit for 1/8 inch thick steel walls on the tanks. A 10 inch diameter of fissile material is maintained (actual tank OD), while the wall thickness is based on the volume of steel present in the actual tank, i.e., 9.75 inch ID and 10 inch OD. This assumption maximizes the fissile material present and does not overectimate the amount of steelin the tank walls. The results of these calculations l show a kh plus 2a of 0.953, which is slightly greater than the 0.95 limit for normal j
conditions, but less than the 0.97 limit for abnormal conditions. It should be noted i
j that these teks normally contain less reactive UNH and no mechanism has been I identified whicn would result in significant amounts of UO being transferred to 2
! them.
f Additionally, the UNH tanks were evaluated at various UNH concentrations. ARH-600 shows that optimum UNH concentration occurs between 700 and 1100 g U/l.
i I
i in these calculations, no credit was taken for the steel walls. The maximum calculated k,,, plus 2e for this model is 0.816, well below the 0.95 limit. This reacti'.cy occurs at a UNH concentration of 1,060 g U/l.
l
- Boiler -
Tha boiler, which provides steam to the pellet dissolver, does not contain fissile
- material. However, if the steam pressure collapses, a vacuum could be drawn on l the piping to the pellet dissolver.
- Criticality safety for the boiler is maintained by its safe geometry.
1 I
Summarv of Accident Conditions l
l The actual dimensions of the boiler are 10.25 inch ID and 16,75 inch inner height l
i and it was assumed to be filled with 1,060 gU/l UNH. K.,, under these conditions is O.853, including 2o.
l le Vac-U-Max Transfer Filter and Drio Pans The Vac-U-Max filter collects UO " dust" from the transfer system and the 4 inch l
2 deep drip pans are catch basins for the dissolver, oxidation, pump and dump tanks j
on the north side of the room and the lag storage tanks on the west side of the i
room.
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t AMENDMENT APP.5ATION DATE:
PAGE NO.:
August 12,1998 15-138c l
sPC-ND.3330 947 (R-1/07/92)
Siemens Power Corporation - Nuclear Division
{
eur-2 SPECIAL NUCLEAR MATERIAL LICENSE NO. SNM 1227, NRC DOCKET NO. 70-1257 PART II-SAFETY DEMONSTRATION REV.
41 Criticality safety for these components is maintained through safe geometry.
Summarv of Accident Conditions l
' The effects of these components were calculated in the analysis of interactions of l
components in Room 52.
l l
The evaluation of neutron interaction between respective tanks used a KENO.Va 1
{
model of the entire room. The following is a description of the general model:
l I
- The pellet dissolver, oxidation tank, separator and funnel, half-full 5-gallon bucket (28.9 kgs UO of 5 wt.% U s) at vacuum transfer station, and 23 2
Vac-U-Max filter contain an optimum heterogeneous UO -H O mixture.
i 2 2
- The UNH tanks are filled with the optimum 1,060 g U/l UNH solution.
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The two 4 inch deep drip pans (one along part of the north wall and one l
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along part of the west wall) are filled with 1,060 g U/l UNH solution. The drip pans contain the bottom 4 inches of the tanks which sit in them.
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- Concrete reflection is used for the six sides of the room.
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- The interspersed moderation in the room was varied from dry to fully flooded. The
! results show that the room is adequately subcritical with a maximum k,n of 0.930 l (including 20) The maximum reactivity occurred with 99% interspersed moderation.
l l
l A calculation was performed to address the interaction of a 5-gallon bucket of l
pellets (28.9 kg UO ) passing over the Vac-U-Max filter. The maximum k,n under i
i 2
this condition is 0.888 (including 2a), which is adequately suberitical.
l Abnormal conditu ns are the same as normal conditions, with the addition of a 5
~
I gallon bucket of UNH located between the pump and dump tanks and between the lag storage tanks. The buckets were filled with UNH solution at a concentration of l
1,060 g U/l. No credit is taken for the steel walls of the buckets. For the system i
! under abnormal conditions with 5 wt% 2asU, the maximum k,n is 0.925 (including l
20), which is adequately suberitical.
i 15.3.2.3 Radiation Protection Gadolinia scrap recovery is performed in a limited access radiation controlled area.
Personnel entering the area, who require monitoring under 10 CFR 20.1502(a), are !
required to wear radiation monitoring devices and protective clothing / equipment j i
- AMENDMENT APPUCATON DATE:
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i August 12,1998 15-138d sPc ND-3330.947 (R-UO742)
4 Siemens Power Corporation'- Nuclear Division
- eur.2 SPECIAL NUCLEAR MATERIAL LICENSE NO. SNM-1227, NRC DOCKET NO. 70-1257 PART 11-SAFETY DEMONSTRATION REV.
41 appropriate for the work to be performed. Personnel are required to survey themselves prior to exiting the controlled area. Equipment leaving the controlled area must be released by Radiological Safety personnel. All personnel also receive initial and yearly refresher training on radiation protection principles and requirements.
Airbome uranium contamination is controlled by extensive use of hoods which are j
maintained at negative pressure and ventilated to the POG or DOG system. An example of such a hood location is a dissolver tank hood.
I Routine surveys are performed and housekeeping practices are enforced to minimize surface and airbome contamination in the processing areas. Air is continuously sampled I
and periodically analyzed to detect any airbome contamination.
l l
! Urine sample analyses and lung counts are periodically performed for personnel who work i
l in the controlled access area. The frequencies of such testing are described in Chapter 3.
! 15.3.2.4 Fire Protection I
I The ELO Building is rated as noncombustible. Monthly inspections confirm that fire loading is kept to a minimum. Fire extinguishers, alarm pull boxes, and heat detectors are strategically placed throughout the process areas.
15.3.2.5 Environmental Safety l Hazardous materials are contained to prevent their introduction into the I environment. All unit operations are served by POG vent lines or by hoods. Hoods I
are maintained at a negative pressure and vented to the POG or DOG system.
l l Floors are sealed and have no drains.
l The POG and DOG systems treat and remove fumes and particulates from the i
! exhaust air using scrubbers, dryers and two stages of high efficiency filtration i
i (HEPA).
All room and building air is processed through the heating, ventilation, and air i
! conditioning system and then HEPA filtered to remove particulates.
I 3
[
Certain chemically hazardous solid wastes may be disposed of in special containers !
distributed throughout the process area. These wastes are treated as hazardous !
mixed waste as appropriate and periodically transferred to a secured storage area !
l for future disposal. L4.uid chemical wastes are typically routed to the surface i
impoundment system which is appropriately designed, constructed, and operated to I
provide safe and effective storage / treatment of these effluents.
l l AMENDMENT APPLCATON DATE:
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August 12,1998 15-138e i
sPC-ND:3330 947 (4UO7/92)
Siemens Power Corporation - Nuclear Division eup.2 SPECIAL NUCLEAR MATERIAL LICENSE NO. SNM-1227, NRC DOCKET NO. 70-1257 PART 11 -SAFETY DEMONSTRATION REV.
41 15.3.3 ELO Drain System The ELO drain system collects various liquid waste streams which are ge.'erated in the ELO Building. Some of these sources originate in rooms that are safe batch workstations.
These sources normally do not contain significant quantities of uranium compounds; however, they have the potential to contain up to a safe batch of uranium.
Liquid waste streams received by the ELO drain system are then i
,, discharged to Lagoon 3 which is an unfavorable geometry system. The system is operated such that all liquid waste discharges must contain s 1000 ppm U.
The main compounds are:
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August 12,1998 15-139 sPc-ND:3330 947 (R-1/07/92)
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Sismens Power Corporauon - Nuclear Division EMF 2 SPECIAL NUCLEAR MATERIAL LICENSE NO. SNM-1227, NRC DOCKET NO. 70-1257 PART ll-SAFETY DEMONSTRATION REV.
i i 36 i
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7 5.4 se DesE/ '" M Acavut PLAN.$
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ACRTUC PLAN l,,,, l j
- = = * * -
-.-a u o,,,,,
i num mw FIGURE ll-14.1 PNL CRITICAL EXPERIMENT LAYOUT (REFERENCE 6) auswouewT apetcarow cars:
October 28,1996 14-17 SPC-ND 3330 947 rA 1/0712)
SiemenS Power Corporation - Nuclear Division eur.2 SPECIAL NUCLEAR MATERIAL LICENSE NO. SNM-1227, NRC DOCKET NO. 70-1257 PART ll-SAFETY DEMONSTRATION REv.
41 Cases 001,002, and 003 determine the critical size of one cluster. Cases 004 and 032 are arrays of three clusters. A description of these clusters is provided in Table 11-14.5.
. TABLE ll 14.5 PNL CRITICAL EXPERIMENT DATA ON CLUSTERS OF 4.29 WT% U2n ENRICHED U0 RODS IN WATER")
2 FUEL CLUSTERS l'
NUMBER LENGTH x WIDTH CRITICAL SEPARATION IN 25.40 mm SQUARE BETWEEN FUEL EXPERIMENT i
ARRAY <23 PITCH (FUEL RODS)
CLUSTERSS)(Xc, mm)
NUMBER 1
10 x 11.51 + 0. 04 m
001 1
9 x 13.35 0.01 m
003 1
8 x 16.37
- 0.03 m
002 l~
3 15 x 8 106.4 i 0.1 004 3
15 x 8 106.0 i 0.1 032W WError limits shown are one standard deviation.
l (2> Clusters of fuel rods aligned in a single row.
j
- Perpendicular distance between the cell boundaries of the fuel clusters.
l-WRerun of Experiment 004.
I s
, The critical size of cases 001,002, and 003 was interpolated based on experiments with I integral numbers of rods per edge; the critical number had a fractional number of rods l
I on one edge and either 8,9, or 10 rods on the other edge. These three cases were ;
- modeled using cell-weighted cross-sections. A suffix "x" on the case name was used to l l
- denote cases modeled with cell-weighted cross-sections.
i Additional cases are described as follows:
Experiment 004 involved three 15x8 clusters with no absorber plates.
Experiments 007,008,013, and 014 involved three clusters with 304L steel absorber i
platesc Two plate thicknesses and different absorbe spacings from the central cluster i were tested.
i Experiments 009,010R,011, and 012 are similar to the previous four except that the I
304L steel contained either 1.05 or 1.62% boron.
i l
l Experiment 031 involved three clusters with BORAL absorber plates.
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AMENDMENT APPLCATONDATE:
PAGE NO,:
i SPC-ND:3330 947 (R 1/07/92)
l.
SiemenS Power Corporation - Nuclear Division suF.2 SPECIAL NUCLEAR MATERIAL LICENSE NO. SNM-1227, NRC DOCKET NO. 70-1257 PART 11 - SAFETY DEMONSTRATION REV.
41 l
CHAPTER 10 FACILITY DESCRIPTION l
10.1 Plant Layout l
l The Sicmens Power Corporation (SPC) Engineering and Manufacturing Facility at Richland consists of buildings and various outside facilities which are shown on Figure ll-10.1.
Many of these buildings, such as. the Office Complex, Guardhouse, Warehouse Complex, etc., are not utilized for uranium processing and are not
, addressed further.
i
- i. Those facilities which are involved with enriched uranium handling and processing, L
and are therefore covered under this License Application, are listed below 1.
Specialty Fuels (SF) Building i
2.
Uranium Oxide (UO2) Building 3.
Engineering Laboratory (ELO) Building j
4.
Dry Conversion (DC) Building i
5.
Contaminated Clothing Laundry 6.
Fuels Storage Warehouse (Bay 4) 7.
UNH Drum Storage Warehouse I
8.
Radioactive Materials Storage Warehouse (Bay 6) 9.
Materials Warehouse (Bay 2) 10.
Product Development Test Facility (PDTF) 11.
UF Receiving and Storage Facility l
12.
Operations Scrap Warehouse (Bay 7) l 13.
UF. Cylinder Recertification Facility
[
14.
Waste Storage Facility i
15.
Lagoon Uranium Recovery and Solids Processing (LUR/SP) Facility 16.
Ammonia Recovery Facility (ARF) 1
! A description of these facilities, including the licensed activities in each, follows. The I
LUR/SPF and ARF are described in Section 10.4, Radioactive Waste Handling.
1 All buildings and facilities on the SPC site were designed, constructed and inspected I
-l in accordance with the edition of the Uniform Building Code (UBC) current at the time l l
i
- of construction, the City of Richland Municipal Code, plus any special requirements as may have been dictated by their intended use.
Unless otherwise indicated, the !
i facilities were all designed to withstand UBC Zone ll seismic loading and 20 lb/ft 2
windward pressure.
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I AMENDMENT APPLCATON DATE:
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July 8,1998 10-1 sPC-ND:3330 947 (R-1/07/92)
Siemens Power Corporation - Nuclear Division eup.2 SPECIAL NUCLEAR MATERIAL LICENSE NO. SNM-1227, NRC DOCKET NO. 70-1257 PART ll-SAFETY DEMONSTRATION REV.
41 i
All buildings are equipped with rate-of-rise / fixed temperature heat detectors for fire detection. These detectors activate a local alarm, an alarm at the Guard Station and an alarm at the City of Richland Fire Department. All buildings also are equipped with hand-held fire extinguishers.
I i
10.1.1 SF Buildina Description i
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1 1
- The SF Building is 2-stories (approximately 28 ft high) with outside dimensions of 100 x i
114 ft plus a 26 x 126 ft addition to the south side of the building to house the NAF l
furnace (see description of NAF furnace addition below). The first and second floor plan i
- ~ ~ views are shown on Figure 11 - 10.2. The outside walls are 6-in thick, precast, reinforced i
concrete slabs attached and sealed to reinforced concrete columns. The roof is made of steel deck plates supported on steel trusses and covered by a vapor barrier insulation, plus l a 20-year, built-up, low-melt asphalt roof with a final coating of gravel. The inner side of i; the precast wall panels are insulated and covered with fire-rated gypsum board. The gypsum panel joints are taped and sealed and the interior surfaces are suitably painted.
I i The compressive strength of all concrete exceeds 3000 psi and the 6-in thick concrete !
I floor slabs were designed for 250 psf. A storage vault 15 x 17% x 26 ft high occupies l the northeast corner of the building. The vault is of reinforced concrete with a minimum wall thickness of 18 in. A large airlock (18% x 28 x 14 ft high) made of concrete block is on the east side of the building and is used as the main entrance to the Solid Waste
. Uranium Recovery (SWUR) Facility located in Room 173.
I 1 The first floor of the 2-story section of the SF Building contains change rooms, spectrometer facilities, radiological safety facilities, and the lower half of the vault. The I l
upper floor contains offices, a lunchroom, heating and ventilating equipment, and the l
{
upper half of the vault.
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- The main processing area is a high bay 76 x 100 ft with interior partitions for process l
- control. The main processing area contains the SWUR Facility and the nuclear absorber l
1
! fuel (Gd 0 -UO ) fabrication line.
2 3 2
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Residual plutonium-contaminated waste, left over after the decontamination in 1985 of i
i the Mixed Oxide (MO) equipment and Room 173, is stored in sealed containers in the l
autoclave pit in Room 162.
i 4
The emission and ICP spectrometers in Room 164 are used to check impurity levels while the mass spectrometer is used to check isotopic levels of SPC's fuel.
i q
The Nuclear Absorber Fuel (NAF) Rod Fabrication Facility is contained in Rooms 160,162 and 163.
The following processes are accomplished in this facility:
Gd 0 -UO, 2 3 j]
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I July 8,1998 10-2 l
sPC-ND.3330.947 (R 1/07/92) m
Siemens Power Corporation - Nuclear Division EMF-2 SPECIAL NUCLEAR MATERIAL LICENSE NO. SNM-1227, NRC DOCKET NO. 70-1257 PART 11 - SAFETY DEMONSTRATION REV.
41 above the mechanical room, and a multipurpose room above the Maintenance Room.
The rooms not connected to the main HVAC system have independent temperature control and ventilation systems. Walls between the rooms are of concrete block of gypsum board on metal stud and track construction.
10.1.5 Contaminated Clothina Laund_ry The location of the Laundry Facility is shown on Figure II - 10.1. The building is a
', combination of a pre-engineered metal building (20 x 30 x 12 feet high) and a concrete block structure (16 x 20 x 11 feet high) with a 6'9" x 17'9" airlock which
.i provides for access, yet maintains the proper pressure differentials for contamination control. The exterior walls are 26-gauge sheet metal and concrete block and the roof l is 24-gauge sheet metal, and built up metal insulated and finished on the interior. The j
i
- interior of the roof is a suspended metal ceiling grid with acousticallay-in panels 5/8-in j
! thick. The interior of the metal walls are finished with fire-rated gypsum panels.
j
. Interior partitions are fire-rated gypsum panels.
Interior partitions are fire-rated l
gypsum board on metal studs. Care was used in sealing the sheet metal and gypsum l
panels in order to maintain the required pressure differentials and airflows in the metal structure. All interior surfaces are taped and sealed and suitably painted. The floor l was made of 3000 psi concrete and designed for 250 psf.
i Contaminated clothing is cleaned in a water wash system, surveyed for contamination, and returned to use. The effluent is directed to retention tanks where l l
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it is sampled prior to being emptied either to the site lagoon system or the City sewer.
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10.1.6 Fuels Storace Warehouse
}
l l ' The location of the Fuels Storage Warehouse is shown on Figure 11 - 10.1.
The !
i building is a pre-engineered metal building 60 x 40 x 16 ft eave height. The exterior l I walls are 26-gauge sheet metal and the roof is 24-gauge sheet metal. The interior of i
} the walls and roof are fully sealed with closure strips and insulated. The floor slab l i
was made of 3000 psi concrete and designed for 250 psf.
I l
The warehouse is used for the storage of packaged special nuclear material in vanous j
, compounds and forms.
i 10.1.7 UNH Drum Storace Warehouse i
The location of the UNH Drum Storage Warehouse is shown on Figure ll - 10.1. The building b :: pre-engineered metal building 100 x 50 x 16 ft eave height. The exterior l l
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l 4 AMENDMENT APPLICATION DATE:
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July 8,1998 10-9 sPC-No3330 947 (R UO7/92)
1 Siemens Power Corporation - Nuclear Division suF.2 SPECIAL NUCLEAR MATERIAL LICENSE NO. SNM-1227, NRC DOCKET NO. 70-1257 PART ll-SAFETY DEMONSTRATION REV.
41 walls and roof are 26-gauge sheet metal. The interior of the walls and roof is fully sealed with closure strips and insulated. The floor slab is made of 3000 psi concrete and designed for 250 psf. The floor stab has a 6 inch curb and is coated to provide secondary containment and facilitate decontamination of possible spills or leaks. The warehouse is used for the storage of packaged special nuclear material in various I
compounds and forms.
10.1.8 Radioactive Materials Storqge Warehouse The location of the Radioactive Storage Materials Warehouse is shown on Figure 11 -
t 10.1. The building is a pre-engineered metal building 50 x 140 x 16 ft eave height.
j The exterior walls are 26-gauge sheet metal and the roof is 24-gauge sheet metal.
l The interior of the walls and roof are fully sealed with closure strips and insulated.
i
! The floor slab was made of 3000 psi concrete and designed for 250 psf. The warehouse is used for the ' storage of packaged special nuclear material in various i
compounds and forms.
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10.1.9 Materials Warehouse (Say 21 i
i The location of the Materials Warehouse is shown on Figure ll - 10.1. Bay 2 of the building is a pre-engineemd metal building 50 x 240 x 16 ft eave height. The exterior l
walls are 26-gauge sheet metal and the roof is 24-gauge sheet metal. The interior of the walls and roof are fully sealed with closure strips and insulated. The floor slab f was made of 3000 psi concrete and designed for 250 psf. The warehouse is used for i
! the storage of packaged special nuclear materialin various compounds and forms.
l 10.1.9.1 Ancillary Radioactive Material Storaae l
l i
i i On occasion, additional storage for uranium oxide product materialis required. During l l
those occasions, pre-engineered enclosures such as enclosed sea containers or trailers l are used. These temporary warehouses are weather-tight and are positioned such j
! that criticality alarm coverage is provided by existing detector units.
j 10.1.10 Product Deyclooment Test Facility (PDTF) i The location of the PDTF is shown on Figure 11 - 10.1. The building is a high bay, 29-.
ft eave height, pre-engineered metal building 80 x 40 ft. The exterior walls are 26-- l gauge sheet metal and the roof is 24-gauge sheet metal. The interior of the walls and '
roof are fully sealed with closure strips and insulated. A concrete pit (15 x 8 x 18 ft !
deep) inside the building provides space for various test vessels and piping systems.
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PAGE NO.:
I July 8,1998 10-10 sPc ND3330.947 (R-907/92)
Siemens Power Corporation - Nuclear Division EMF-2 SPECIAL NUCLEAR MATERIAL LICENSE NO. SNM-1227, NRC DOCKET !
70-1257 PART 11 - SAFETY DEMONSTRATION REV.
41 All concrete used in the construction of the building had 3000 psi compressive strength and the floor slab was designed for 250 psf. A 3-ton bridge crane and hoist services the entire interior of the building. Adjacent to, and constructed as part of the main building, is a 40 x 20 x 12 ft high addition made of the same material as the main building which houses the process boiler.
The PDTF houses an hydraulic test loop that is used to determine heat transfer performance of nuclear fuel assemblies during spray and reflood cooling following a j postulated loss-of-coolant accident (LOCA).
_ L10.1.11 UF. Receivina and Storace Facility f The location of the UFe Receiving and Storage Facility is shown on Figure 11 - 10.1.
t The complete facility consists of:
- 1) an open-air, 5-ton bridge crane and hoist supported by a steel structure which operates over an area of 165 x 25 ft: 2) a 10 x i
10 x 10 feet high sheet metal scale house; and 3) an asphalt area of approximately
! 8500 ft: used for storage of UFe cylinders.
The open-air bridge crane is used to load and unload UFe cylinders on and off semi-i trucks. The crane structure provides an under-crane storage area of about 4000 ft where the UFe cylinders can be moved using the 5-ton crane and hoist. The truck access bay and a total of approximately 1700 ft is provided with a sheet metal rain l cover. The scale house provides a weatherproof structure for the certified scales used
! to weigh full and empty UFe cylinders. An additional asphalt storage area of 2
approximately 9000 ft is provided near the crane structure where UFe cylinders can l
be handled with a forklift. The entire facility provides load, unload and storage capabilities for up to 180 UFe 30-inch cylinders, p
, 10.1.12 Operations Scrap Warehouse The location of the Operations Scrap Warehouse is shown on Figure ll - 10.1. The building is a pre-engineered meta! building 70 X 100 X 16 ft eave height. The exterior walls are 26-gauge sheet metal and the roof is 24-gauge sheet metal. The interior of the walls and rocf are fully sealed with closure strips and insulated. The floor slab was made of 3000 psi concrete and designed for 250 psf.
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The warehouse is used for the storage of packaged special nuclear material in various l
compounds and forms.
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PAGE NO.:
i July 8,1998 10-11 l
sPc-ND'3330 947 (R-1/07/92) l
Siemens Power Corporation - Nuclear Division s u r.2 SPECIAL NUCLEAR MATERIAL LICENSE NO. SNM-1227, NRC DOCKET NO. 70-1257 f
PART ll-SAFETY DEMONSTRATION REV.
41 e
10.1.13 UF Cylinder Recertification Facility -
3 The location of the Cylinder Recertification Facility is shown on Figure II - 10.1. The 1
building is a pre-engineered metal building 30 X 60 X 14 ft sloped eave height. The building is constructed with a sealed, insulated exterior-interior metal wall sandwiched
~ constructed system that maintains pressure of not greater than negative 0.05 inch, water
- gauge, with all doors closed when exhausting 500 cfm of air. The floor slab was made of
- l. 3000 psi concrete and designed for 250 psf.
..i The Recertification Facility will be used to hydrostatically test, intemally inspect, measure.
- wall thickness and leak test Model 30 B cylinders that have been washed in another facility -
l - o(the UO Building) to remove the UF. " heel" that remains in the cylinde 2
f the cylinder have been evacuated. The facility will be capable of certifying 11 cylinders j at a time.
j 10.1.14 Waste Storane Facility The locatio.1 of the Waste Storage Facility is shown on Figure il - 10.1. The pad is an
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asphalt pad 45 X 60 ft with a pre-engineered metal 3-sided building i
30 X 30 X 16 ft. sloped eave height centered on one side of the pad. The exterior walls are 26 gauge sheet metal and the roof is 24-gauge sheet metal.
The storage pad is used for.the storage 'of containerized solid wastes classified as low-I
.i level radioactive, chemically hazardous, or mixed low-level radioactive / chemically y
,j hazardous.
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,i AMENDMENT APPLCATION DATE:.
PAGE NO.:
July 8,1998 10-11 a SPC-ND 3330.947 (R-UO7/92)
SiemenS Power Corporation - Nuclear Division eup.2
.SPECIAL NUCLEAR MATERIAL LICENSE NO. SNM-1227, NRC DOCKET NO. 70-1257 PART 11 - SAFETY DEMONSTRATION REV.
41 10.2 Utilities and Suonort Systems in the day-to-day operation of a nuclear fuels fabrication plant, many utilities and support systems are required. Utilities are required for the manufacture of the fuel and for the protection and safety of the product as well as the employees. A brief description of the - following utilities and/or services is provided in this License Application.
1.
Electric Power i
2.
Compressed Air
._ _j-3.
Water 4.
Sanitary Sewer System 5.
Gas and Chemical Storage i
6.
Communications and Annunciations 7.
Breatning Air
, 10.2.1 Electrical Power i
The electrical power for the SPC plant site is provided by the City of Richland industrial system. In addition, SPC has installed a standby emergency system to i
supply certain plant power needs in case the municipal system fails. Both systems are described in this section.
10.2.1.1 Utility (Normal) Supolv l The normal supply is a 12.5 kV underground cable which connects to a Richland
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! substation bus dedicated to north Richland industrial loads.
The bus is directly supplied through two breakers and a transformer from a 115 kV Bonneville power loop. The _115 kV loop is, in turn, supplied by Columbia River and Snake River hydroelectric generation.
j i-l The normal 12.5 kV cable forms an underground loop within SPC's plant site and each
! plant building supply is tapped into the loop through a 3-phase, 12.5 kV J
. qrounded-wye to 480/277V grounded-wye transformation.
I l 10.2.1.2 Standbv (Emeroency) Supolv Standby emergency power is provided by two diesel-fueled 500 KW generators and !
one 500 KW diesel generator, and one propane fueled 12.5 KW generator. All l t
generators are 3 phase, grounded-wye connected to supply regulated 480 Volt,60 l
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[ AMENOMENT APPLCATON DATE:
PAGE NO.;
j July 8,1998 10-12 sPC-ND:3330.947 (R-1/07/92)
r-SiemenS Power Corporation - Nuclear Division eup.2 SPECIAL NUCLEAR MATERIAL LICENSE NO. SNM-1227, NRC DOCKET NO. 70-1257 l
l PART ll-SAFETY DEMONSTRATION REV.
41 Hz power. Upon a loss of normal power, the ignition systems and battery-driven starters for these generators are autcrr.atically energized and automatic transfer switches cause the generators to supply power to emergency loads.
I Both 500KW diesel generators are located outside the east side of the dissociated f
l located on the west supplies standby electrical service to the north and south
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ammonia facility. Each has a fuel tank with a 500 gallon capacity. The generator j
! the UO Building. The generator located on the east supplies standby electrical l
2 l service to the east end of the UO Building and the Dry Conversion Building.
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l The 12.5 KW generator, located west of the Specialty Fuels Building, supplies power to the security radio and emergency lighting in the Central Guard Station.
l 10.2.1.3 UO, Buildina Normal utility supplied 480/277 V power is fed into the UO Building via three 2500 I
l 2
KVA transformers. North UO normal power is fed from a transformer located on t
2 j the NW corner of the facility. This transformer feeds a 4000 amp switch house also i
located on the NW corner. This switch house distributes power to one 2000 amp i
and two 1600 amp distribution panels located in room 200. South UO normal I
2 power is fed from a transformer located on the SE corner of the facility. This l
transformer feeds a 3000 amp main switch gear cabinet located in room 230. East UO normal power is fed from a transformer located on the center east side of the 2
! facility. This transformer feeds a 3000 amp main switch gear cabinet located in room 201 A. Each of the three normal power services described above has an j
associated standby power service. This power is supplied from the diesel i
generators described in section 10.2.1.2. North UO standby power is fed from the 2
west standby diesel generator. This generator supplies 400 amp service to distribution Panel E via an automatic transfer switch (ATS) both located in room i
- ~ 200. The critical loads fed from this panel are as follows
North UO, Buildina Exhaust Fans K9-16-1 and K9-16-2 i
ROLM Telephone System in OB#5 I
e Vaporization Room 1 Scrubber e
Emergency Lights i
i Lines 1,2,3 and 4 Sintering Furnace Control Power e
Criticality Howler Comparator Panels, Control Panels and Howlers i
e Hydrogen Detection Panel
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July 8,1998 10-13 l
sec-ND.3330 947 (R-1/07/92)
Siemens Power Corporation - Nuclear Division Eur-2 SPECIAL NUCLEAR MATERIAL LICENSE NO. SNM 1227, NRC DOCKET NO. 70-1257 PART ll-SAFETY DEMONSTRATION REv.
41 HVAC Control Panels Various 120 VAC Receptacles 1
South UO2 standby power is fed from the west standby diesel generator. This generator supplies 400 amp service to motor control center MCC-E1 via an ATS both located in room 230. The criticalloads fed from this panel are as follows, i
South UO, Buildino Closed Loop Cooling Pumps e
_.1-Air Compressor #3 DlW Pumps Air Sampling Vacuum Pump I
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Exhaust Fans K3-2-1 and K3-2-2 l
l HVAC Control Panel Instrument Air Dryer I
Hydrogen Detection Panel e
i Autoclave Sump Pump e
i Emergency Lights Various 120 VAC Receptacles
l East UO2 standby power is fed from the east standby diesel generator. This
} generator supplies 400 amp service to motor control center MCC-NE via an ATS I
both located in room 201 A. The criticalloads fed from this panel are as follows:
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Line 2 UO, Buildino l
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Air Sampling Vacuum Pumps 1
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Process Offgas Exhaust Fans K32-16-1 and K32-16-2 l
Line 2 Calciner Tube Drive and Rotary Airlock Valve l
e Exbaust Fans K31-16-1 and K31-16-2 Line 2 Control System Un-Interuptable Power Supply Hydrogen Detection Panel 1
i e HVAC Control Panels l-Vaporization Chest Control Panels
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I Instrument Air Dryer I
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M1, d2 and M3 Scrubber Pumps e
Ammonia Recovery Facility Micon Control Pandl#16 and HF control I/O ARF Sump Pump i
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l l AMENDMENT APPLCATON DATE:
PAGE NO.:
l July 8,1998 10-14 I
sPc-ND.3330.947 (R-1/07/92)
I
Siemens Power Corporation - Nuclear Division eur.2 SPECIAL NUCLEAR MATERIAL LICENSE NO. SNM-1227, NRC DOCKET NO. 70-1257 j
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PART ll-SAFETY DEMONSTRATION REV.
j 41 Safety Shower Lights Various 120 VAC receptacles Heat trace Emergency Lights NOX Stack Camera 10.2.1.4 SF Buildina
- SF Building normal power is fed from a 1500 KVA transformer located on the east side of the facility. Th
- s transformer then feeds two 1600 amp switch houses also I
.. ' located on the east side of the facility. One of these switch houses feeds the north side of the building. The other feeds the south Furnace Addition side of the
- building.
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j SF Building standby power is fed from the North UO2 distribution Panel E described l in section 10.2.1.3. This 200 amp service is ultimately powered from the west l
standby generator. The criticalloads served are as follows:
l SF Buildina (Power Fed from North UOy l
e Exhaust Fan K6-2-1 and K6-2-2 i
Air Compressor l
Air Sampling Vacuum Pump SWUR Shroud Cooling Motors, Shutdown Exhauster, Control System and Etch i
Waste Pumps l
HVAC Control Panel Criticality Howler Control Panel and Howlers i
Cooling Tower Heater and Blower.
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Safety Shower Lights 1
I-Heat Trace
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i Emergency Lights I
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. ' Various 120 VAC Receptacles I
10.2.1.5 Dry Conversion Building I
' Dry Conversion Building normal power is fed from a 2500 KVA transformer located i
on the south end of the facility. This transformer feeds 3000 amp service to the i
l main switch gear cabinet located in room 290.
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t AMENDMENT APPLCATON DATE:
PAGE NO.:
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July 8,1998 -
10-15
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SPc-ND:3330.947 (R 1107/92) l
I Siemens Power Corporation - Nuclear Division EMF-2 SPECIAL NUCLEAR MATERIAL LICENSE NO. SNM-1227, NRC DOCKET NO. 70-1257 l
PART ll-SAFETY DEMONSTRATION REV.
i 41 Dry Conversion Building standby power is fed from the east standby diesel generator. This generator supplies 800 amp service to motor control center MCC E j
via an automatic transfer switch (ATS) both located in room 290. The critical loads fed from this panel are as follows:
l Drv Conversion Buildina Air Sampling Vacuum Pumps P6-60-1 and P6-60-2 e
Offgas Blowers81-608, B2-608, and 83-608 Exhaust Fan K62-16-1 and K62-16-2 i
Calciner Tube Drives V1-403, V2-403, V3-403 e
Dry Conversion Control System Un-interuptable Power Supply e
Criticality Howler Control Panel and Howlers 4
Fire Alarm Control Panel e
l Hydrogen Detection Panel HVAC System Control Panel i
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Cooling Tower P-640 Pumps, Fan and Heater e
j Supply Fans K61-10-1 and K61-10-2 i
e Various 120 VAC receptacles e
Emergency Lights 10.2.2 Comoressed Air System The Plant's compressed air system is actually four systems:
normal plant air,
, ' instrument air, control air and emergency air.
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The nuclear fuel manufacturing portion of the plant's normal compressed air needs are supplied by three compressors located in the Compressor Building shown on Figure
! 11-10.1. These compressors supply air to the UO, SF, ELO Buildings, and the ARF.
2 s
Other facilities such as the Maintenance Building, Machine Shop and PDTF have small compressor units to serve their individual needs.
t Two of the compressors in the Compressor Building are 500 CFM units and the third is a 413 CFM unit which provides a total capacity of 1413 CFM for the manufacturing l portion of the plant. All three units are classifiad as " oil-free". Normal plant demand
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l is satisfied by running any two of the units with the third on standby. The system pressure is maintained at 115 psig.
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! AMENDMENT APPLCATON DATE:
PAGE NO.:
July 8,1998 10-16 sPc-ND:3330 947 (R 1/07/92)
i Siemens Power Corporation - Nuclear Division eup.2 SPECIAL NUCLEAR MATERIAL LICENSE NO. SNM-1227, NRC DOCKET NO. 70-1257 PART ll-SAFETY DEMONSTRATION REV.
7 41 Normal compressed air is supplied to air dryers located in the North, South, and East Equipment Rooms of the UO Building, and in the ARF. The dryers dry the air to a 2
dewpoint of -40 F, and then it is distributed as instrument air.
Instrument air is reduced in pressure to 20 psig to be utilized as HVAC and process equipment control air.
In the event of an electrical power outage, the plant's emergency air system will function.
7 The emergency system consists of the 413 CFM unit in the Compressor Building, a 42 CFM unit in the north equipment room of the UO Building, and a 34 i
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July 8,1998 10-17 l
sPc-ND.3330 947 (R-1/07/92)
s i
. SiemenS Power Corporation - Nuclear Division ag.a SPECIAL NUCLEAR MATERIAL LICENSE NO. SNM-1227, NRC DOCKET NO. 70-1257 l
PART11-SAFETY DEMONSTRATION REV.
l 36
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CFM unit in the south Equipment Room of the UO Building._ All three of these units l 2
t : are connected to the plant's. emergency power system. The 413 CFM compressor
[ provides air to'the plant until the various systems can be safely shut down. The i
smaller units in the equipment rooms are devoted exclusively to the HVAC systems to provide sufficient operating and control air to allow the system to be shut down safely
)
[ or to continue to operate in the emergency mode.
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10.2.3,Wgg
! ' The water supply to SPC is furnished by ' he City of Richland._ The source of water for t
l Richland is the Columbia River. Wells / which were the' earlier source of water for Richland before construction of the present water filtration plant on the river, have
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been kept in operable condition as a secondary backup source. Primary backup is
' fumished by a 15,000,000-gallon equalizing reservoir on a bluff south of Richland at an elevation of 545 ft.
_ Water is supplied to the plant via two lines from the North Richland water grid into the plant's water loop. The City of Richland's Water Department has assured SPC that each main line would supply in excess of 1500 gpm at 40 psig for a total capacity in l
- excess of 3000 gpm through both lines. Actual flow measurements taken during the t
' entire 1991 year show that the maximum water required by the plant was l
- approximately 280 gpm with a yearly average of 189 gpm.
[ The plant's total water usage averages 42 gpm of sanitary water and 147 gpm of process water. Approximately 20 gpm (maximum usage) of the process water is i further refined as deionized water for various product and laboratory uses.
- Since both sanitary and process water needs are taken from the same inlet waterline, vacuum breakers are installed to provide assurance that process water cannot backflow into either the city system or into the plant sanitary water system. Figure 1110.18 shows the main waterlines into'and around the SPC facility.
1 Due to the redundant backup systems for Richland's water supply, the probability of complets loss of water supply is extremely small. Since the water is supplied to the fuels plant by a complete loop with a number of sectionalizing and isolation valves, the-probability of a water outage due to a main pipe breakage is also considered i
extremely remote. Even if a complete water outage did occur, the only possible I
damage to the plant would be to the sintering fumaces and would not present a radiological or containment problem.
. AMENDMENT A%CATON DATE:
' PAGE NQ; October 28,1996 18 SPC.ND.3330 947 ( A407,92) w
SiemenS Power Corporativa - Nuclear Division eup.2 SPECIAL NUCLEAR MATERIAL LICENSE NO. SNM-1227, NRC DOCKET NO. 70-1257 PART 11 - SAFETY DEMONSTRATION REV.
41 1
The. HEPA filter medium is 100% moisture-resistant fiberglass, pleated 'over corrugated separators and sealed in fire-resistant plywood frames. The individual i
filters are certified to remove 99.97% of 0.3 micron particles and meet or exceed 3 Military Specification MIL-F-51079.
10.3.3 UO, Buildina (North) HVAC Systems i
' The UO Building (north) has four air supply systems and four exhaust systems. The 2
supply air systems consist of the following:
The K1 system supplies air to the service areas of the building with a portion of this area being recirculated and a portion being once-through.
The K2 system supplies air to the fabrication areas of the building with a portion of this air being recirculated and a portion being exhausted.
The'K23 system is a once-through system which supplies the uranium scrap and lube-blend areas.
The K36 system is also a once-through system which supplies the UF.-UO Line 2 i 2
conversion areas.
i The exhaust air systems consist of the following:
The K3 building exhaust system provides room and process hood exhaust for portions of the service and fabrication areas which are not recirculated air.
The K9 system exhausts air from the etch room and etch tanks; The K31 exhaust system, which is described in and primarily serves Line 2 conversion, also serves as the non-offgas exhaust for the UF.-UO2 conversion, lube blend and uranium scrap reprocessing areas.
l All final filter banks in the four exhaust systems are tested and assured to have an installed efficiency of 99.95% for 0.8 micron particles. Simplified schematics of these HVAC systems are furnished in Figures 11-10.21 and ll-10.22.
AMENOMENT APPLCATON DATE:
- PAGE No.
July 8,1998 10-29 SPc-ND'3330 947 i A Sio7 921
l Siemens Power Corporation - Nuclear Division EMF-2 SPECIAL NUCLEAR MATERIAL LICENSE NO. SNM-1227, NRC DOCKET NO. 70-1257 PART li-SAFETY DEMONSTRATION REv.
l 41 10.3.3.1 K1 and K2 Air Supolv Systems The K1 system, which supplies air to the service areas of the building, and the K2 system, which supplies air to the fabrication areas, both use partial recirculation.
Recirculated air in the K1 system is only rough filtered while recirculated air in the K2 system is passed through double HEPA filters, of which the second has an installed
' efficiency of 99.95% for O.8 micron particles, Provision is made in the K2 recirculation system for continuous radiation monitoring of i
recirculated air prior to the second filter. An indication of an airborne concentration L exceeding 8 MPC-hr automatically places the K2 system on a once-through basis with the air exhausting through the final filter to the stack.
I The K1 supply system provides approximately 28,600 ft'/ min of air which is divided i among various laboratories, offices, changerooms, HVAC equipment room, and alternately to provide standby capability. Both fans are connected to normal and emergency power.
I 10.3.3.2 K9 Exhaust System The K9 exhaust system provides exhaust service for the corrosive fumes from the fuel rod etch and stop bath tanks. The exhaust is passed through a scrubber, dryer, and I
double HEPA filters and is discharged through a fiberglass-polyester stack 37 ft high.
i The ductwork material in the K9 exhaust system is steel-coated inside with acid-resistant vinyl resin upstream of the scrubbers and stainless steel main ducts and PVC l l
branch ducts downstream.
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j The K9 exhaust system has two full-capacity fans which are used alternately to i provide standby capability. Both fans are connected to normal and emergency power.
! The K9 system exhausts approximately 6000 ft'/ min continuously.
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July 8,1998 10-30 sPC-ND-3330.947 (R-1/07/92)
~
SiemenS Power Corporation - Nuclear Division eur.2 SPECIAL NUCLEAR MATERIAL LICENSE NO. SNM-1227, NRC DOCKET NO. 70-1257 l
PART ll-SAFETY DEMONSTRATION REV.
41 l
10.3.3.3 S_ystem Controls The HVAC systems are controlled with temperature, pressure and flow sensors actuating valving and damper positions to hold temperatures, pressures, and pressure differentials constant in the various building areas. In the event of power failure, K3, K9 and K31 exhaust fans are automatically transferred to an emergency electrical bus.
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The power to the supply fans is interlocked so that exhaust fan failure, or failure of I
i instrument or control air, stops the K1 or K2 supply fans. A similar upset in the K31 l exhaust system will stop the K23 and K36 supply fans. In the event of power failure,
_. '.. the supply fans will stop and air will windmill through the supply fans due to the continuance of the exhaust fans on emergency power.
The differential pressure between the zone containing the building's lobby, stairwell l and changerooms on the first floor, the offices and lunchroom on the second floor, l and the zone comprising the rest of the building will be maintained at a minimum of 0.05-inches water gauge, with the former being at atmospheric pressure, or slightly i
i above, and the latter below atmospheric pressure at all times, i
All main duct filters (K3 and K9 systems) are provided with differential pressure i
indicators. Sudden changes in differential pressures across the final K3 or K9 filter banks indicating either a filter rupture or excessive plugging automatically activate
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alarms.
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{ AVENOMENT APPLCATON DATE:
PAGE NO.:
i July 8,1998 10-31 SPC-ND:3330 947 (R-1/07S2)
SiemenS Power Corporation - Nuclear Division eup.2 SPECIAL NUCLEAR MATERIAL LICENSE NO. SNM-1227, NRC DOCKET NO. 70-1257 PART 11 -SAFETY DEMONSTRATION REV-i 41 10.3.3.4 Deluae System i
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A deluge system of fog spray nozzles is installed in the main exhaust duct (K3) a short l distance upstream of the final filter bank. If rate-of-rise / heat detectors. indicate a - l predetermined temperature rise, the deluge system is automatically activated. Should !
i the deluge system be activated by any circumstance, differential pressure readings across the filter shall be taken and an in-place DOS test made at the earliest i opportunity. The K9 system has liquid scrubbers in-line and ahead of the filters; therefore, they are not equipped with deluge systems.
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.10.3.3.5 Final Filter Banks i
The final filter bank for the K3 sy; tem is encased in a sheet metal housing that, in '
turn, is fastened'and sealed to a concrete slab. HEPA filters rated at 1000 ft / min at !
8 one-inch water gauge pressure drop are mounted on special clean-room frames. The i HEPA filter medium is 100% moisture-resistant fiberglass, pleated over corrugated separators and sealed in fire-resistant plywood frames. The individual filters are certified to remove 99.97% of 0.3 micron particles and meet or exceed Military '
Specification MIL-F-51079.
Following the scrubber, the exhaust air of the K9 system enters a filter plenum which houses both the primary and final HEPA filters. All construction features of the final filter bank of the K9 system are the same as those for the K3 system.
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10.3.4 UO, Buildina HVAC Systems (South Addition) i Although this building addition is physically attarned to the original UO Building, it 2
has its own-separate HVAC system (K20 suppe,, K21 exhaust, and controls). An airlock connecting the two facilities maintains sek aration of the two HVAC systems.
A simplified schematic diagram of the HVAC system for this addition to the UO 2
Building is provided in Figure 11-10.23.
AMENOMENT APPtlCATON DATE.
8 AGE NQ; July 8,1998 10-32 SPC.ND 3330 947 A-1/07 92:
SiemenS Power Corporation - Nuclear Division sup.2 SPECIAL NUCLEAR MATERIAL LICENSE NO. SNM-1227, NRC DOCKET NO. 70-1257 i'
PART ll-SAFETY DEMONSTRATION REV. I 36
! The HEPA filter medium is 100 % moisture-resistant fiberglass, pleated over ;
I l corrugated separators and sealed in fire-resistant plywood frames. The individual !
filters are certified to remove 99.97% of 0.3 micron. particles and meet or exceed Military Specification MIL-F-51079.
10.3.5 UO, Buildina une 2 Conversion HVAC Systems The general features of the UO Building Line 2 conversion HVAC systems are a 2
once-through ceiling-to-floor airflow supply air (K30) system, a double HEPA filtered l
_ UK31) building exhaust system, and a process offgas (K32) exhaust syst' m with '
e scrubbers, dryers, and double HEPA filters.
A simplified schematic of the K30 air supply system, K31 building exhaust system, and K32 POG system is shown in Figure !!-10.22.
10.3.5.1 K30 Air Sunoiv System t
The K30 air supply system supplies approximately 28,000 ft'/ min of 100% outside air to the Line 2 conversion area, UNH facility, vaporization room, control room, and the i
facility's equipment room. Airflows are directional from ceiling to near-floor exhaust air grills or process hood inlets, and always away from areas of low contamination !
potential to areas of higher contamination potential.
10.3.5.2 K31 Air Exhaust System The K31 air exhaust system removes approximately 28,000 ft'/ min of air supplied from the process areas served by the K30 air supply system, and 20,000 ft / min from 2
areas supplied by the K23 and K36 (Figure 11-10.22 and Section 10.3.3) air supply systems. The combined airflow, including infiltration, totals about 50,000 ft / min 2
being exhausted. through the K31 system. The double filter arrangement in this system consists of the final HEPA filter bank plus individual or smaller filter banks of prefilters and HEPA filters in the exhaust ducts of the areas or equipment serviced.
Ductwork in the K31 system is made of galvanized steel.
The K31 system exhaust air passes directly from the final filter bank to the exhaust j
fans and is discharged from a stack extending 22 ft above the highest portion of the UO Building, or 50 ft above ground elevation. The K31 exhaust system has two full 2
capacity fans which are used alternately to provide standby capability. Both fans are connected to normal and emergency power.
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AMENOMENT APPt.iCATION DATE:
PAGE NC..
October 28,1996 10-35 SPC No:3330 947 (Ra C7 92:
l
Siernens Power Corporation - Nuclear Division eup.2 SPECIAL NUCLEAR MATERIAL LICENSE NO. SNM-1227, NRC DOCKET NO. 70-1257 PART ll-SAFETY DEMONSTRATION REv.
41 10.3.5.3 K32 Exhaust System The K32 exhaust system provides approximately 2000 ft / min vent service for equipment, tanks and vessels in the UF and dry conversion processes as well as l
offgas exhaust for the calciner and exhaust service for the UF, vaporizer chests. As in the etch process, fumes from these vessels are corrosive and an exhaust system separate from the main K31 system is required. The exhaust is passed through a scrubber, a dryer, and double HEPA filters and is discharged through a separate stack located on the roof of the UO Building. This stack extends 50 ft above the highest 2
_.iportion of the UO 2 Buil ding. The ductwork material in the K32 exhaust system is
- stainless steel for ducts greater than seven inches in diameter, and polyvinyl chloride I for ducts less than seven inches in diameter.
I The K32 system has two full-capacity fans which are used alternately to provide
_ ! standby capability. Both fans are connected to normal and emergency power. A 1
scrubber is provided to remove ammonia and fluorides from the offgases, a dryer to remove entrained liquids, and HEPA filters to remove potential uranium. In addition to i
the main scrubber in the K32 system, there is a second scrubber in the exhaust line from the calciner.
10.3.5.4 System Controls The HVAC systems are controlled with temperature, pressure and flow sensors actuating valving and damper positions to hold temperatures, pressures, and pressure l l
j differentials constant in the various building areas.
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[ The K31 exhaust fan power is interlocked so that the fans are stopped upon
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! excessive negative pressure (more negative than -14 inches water gauge) and instrument or control air failure. In the event of power failure, the K31 fans are j automatically transferred to an emergency electrical bus.
j The power to the supply fans is interlocked so that a rise in K31 exhaust pressure higher than -8 inches water gauge (exhaust fan failure) or failure of instrument or l control air stops the K30 supply fan. A similar upset in the K31 exhaust system will stop the K23 and K36 supply fans. In the event of power failure, the supply f ans will stop and air will windmill through the supply fans due to the continuance of the f l exhaust fans on emergency power. A rise in exhaust pressure in the K32 system (fan '
failure) higher than -4 inches water gauge automatically shuts down the UFe process, j
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! AMENDMENT APPLCATON DATE:
PAGE NO.:
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