ML20059E141
| ML20059E141 | |
| Person / Time | |
|---|---|
| Site: | Framatome ANP Richland |
| Issue date: | 07/25/1990 |
| From: | SIEMENS POWER CORP. (FORMERLY SIEMENS NUCLEAR POWER |
| To: | |
| Shared Package | |
| ML20059E135 | List: |
| References | |
| NUDOCS 9009100045 | |
| Download: ML20059E141 (87) | |
Text
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AD%$NCEDNUCLEARMELSCORPORATION:
m p.g
~SPECIAL NUCLEAR MATERIAL LICENSE NO SNM _1227, NRC DOCKET NO. 701257 i
i 1
TABLE OF CONTENTS '
REV.'
26 PART I - LICENSE CONDITIONS q
Ea9A F O RWAR D..............................
0-1 I
CHAPTER 1 - STANDARD CONDITIONS AND SPECIAL AUTHORIZATIONS -
1.1 Corporate Information............................,,.
1-1'
-l A
1.2 Site Location................ -.......................
11 1.3.
Ucense Number and P.,;od of Ucense.....................
11 1.3.1 -
Special Nuclear Materials Ucense.............,,........
1 -1 i
1.4 Possession um!ts.................................
1-2 1.4.1 U raniu m-235.......................................
12 J
1.4.2 Plutonium i..
1-2 ll 1.5 Authorized Activities..................................
12 1.6
_ Exemptions and Special Aushorizations.......,.......,.
12-1.6.1 Criticality Accident Alarm System Exemption...............
12 jl 1.6.2 Special Processing of U Enriched From 5 to 19.99 wt% U-235..
1-4 1.6.3' Plutonium Storage...................................
15 1.6.4 Posting Exempticn......................,............
16 1.6.5 Waste Disposal......................................
1-6
-1,6.6
. Special Nuclear. Material Safeguards...........,,.......
1-6 1
1.6.7
- Authorization at Reactor Sites,,.......................
1-7 i
1.6.8 Authorized Release Guldelines............................
1-7 1.6.9 Authorized Criticality Alarm System Outage.,,............
17 CHAPTER 2 - ORGANIZATION AND ADMINISTRATION i
2.1
' Organizational Responsibilities and Authority-.......,,,.....
21
.2.1.1 i%sident and Chief Executive Officer....................
2-1 1
~ 2.1.2 ~
Vice President,' Operations Division......................
2-1 2.1.3 Manager, Manufacturing Engineering,,...................
2-1 L
2.1.4 Manager, Process Engineering.......................
2-2 l
2.1.5 Manager, Plant Engineering.........................
2-2 2.1.6 Manager, Plant Operations.........
2-2 2.1.7 Manager, Quality Control.,,..........................
23
~ 2.1.8
. Manager, Operations Planning and Scheduling.............
23 2.1.9 Manager, Safety, Security, and Ucensing...,,,...........
23 2.1.10 Supervisor, Safety...................................
2-4 2.1.11 Criticality Safety Component...........................
2-4 2.1.12 Health Physics Component.....................
2-5 2.1.13 Radiological Safety Component...
2-5 AMENDMENT APPUCATION DATE:
Pace No:
July 25,1990 I
j.
9009100045 900904 ANF.3830.0S t (6/89) l PDR ADOCK 07001257 C
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J An'nNNC8DNUCLEARMELS CORPORATION
)
m p,7 ie >
~ SPECIAL NUCLEAR MATERIAL LICENSE NO. SNM 1227, NRC DOCKET NO. 701257 j
TABLE OF CONTENTS REv.
26 CHAPTER 2 ORGANIZATION AND ADMINISTRATION (Cont.d)
E_aQ2 a
2.1.14-Health Physics Technicians.........,,. -...........,..
2-6 2.1.15 Manager, Regulatory Cort pliance.......................
27 2.1.16 Vice President, Engineering Division.....................
27 2.1.17 Manager, Research and Product Development 27 2.1.18-Manager, Chemical and Ceramic Development.............
27
'2.1,19 Manager, Materials Research...........................
28.
2.1.20 Manager, Product Development and Testing ~...............
2-8 2.22 Personnel Education and Experience Requirements.........,
28 t
2.2.1 Manager, Safety, Security, and Ucensing..................
29;
~
-(
2.2.2 Manager, Regulatory Compliance.................
2-9; 2.2.3' Supe rvisor, Safety...................................
2-9 2.2.4 Criticality Safety Specialist.,............................
29 2.2.5 -
Health Physics Specialist................,............
29 2.2.6 ~
Health Physics Technicians............................
29
- 2.3 Safety Review Committees......................,.......
2.10 2.3.1 Health and Safety Council.............................
2 - 2.3.2 '
ALARA Committee...................................
2 11' g'
2,4.
Training............................................
2 12 2.4.1
_ Initial Training......................................
2-12 2.4.2 Followup Training...................................
2 12 N
2.4.3 Health Physics Technician Training..,....,...........,,
2-12 L'
2.4.4 '
Training Evaluations...............................
2 13 2.5 :
Operating Procedures, Standards and Guides............
2 13 2.fi
- Internal Audits and inspections.........................
2 13 2.6.1 Radiation Protection.................................
2-13 L
2.6.2.
Criticality Safety....................................
2-14 L
2.6.3 Hazardous Chemical Safety...........................
2 2.6.4 Fire Protection......................................
2 15 c-2.6.5 Environmental Protection Inspections....................
2-15 c
f 2.7 investigations and Reporting of Reportable incidents.........
2 16 l
2.8 Re c o r d s...........................................
2-17.-
. CHAPTER 3 RADIATION PROTECTION 1.g 3.1' Special Administrative Requirements.........
31 1
. 3.1;1 Al. ARA ; Policy......,................................
3-1 3.1.2 Radiation Work Procedures............................
3-1 3.2 Technical Requirements.............................
3-2 M
,3.2.1 Controlled Areas..................................
3-2 m
3.2.2 Ve ntilatio n.....................................
3-3 3.2.3 Work Area Air Sampling.................
3-4 AMENOMENT APPUCATION DATE:
PAGE NO :
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g ANF-3830.051 (6/89)
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'I ADMANCEDNUCLEARMELSCORPORATION p p.y
- SPECIAL NUCLEAR 6ATERIAL LICENSE NO. SNM 1227, NRC DOCKET NO.' 701257' 1
l TABLE OF CONTENTS REV.
26 CHAPTER 3 - RADIATION PROTECTION (Cont.d)
Eggg 3.2.4 Radioactivity Measurements Instruments.............,,..
35 3.2.5 Radiat!on Exposure..................................
3-6 3.2.6 Surface Contamination.,,.,,..........,,,,...........
3-8 3.2.7.
Bioassay Program....,,..................,,........
3 APPENDIX A - ANNEX C..............................
3 14 b
CHAPTER 4 NUCLEAR CRITICALITY SAFETY 4.1 Administrative Conditions....,,.,.,,,.......,,.,,..
41
- j 4.1.1 Process Anklyses (Critically Safe Determinations)...........
41
.4.1.2 Criticality Safety Standards,,.........................
4-2 4.1.3 Fissile Content Verification..,,......,,.,,....,,.,,....
4-2 4.1.4 Special Nucle'ar Material Control 4-2 1
4.1.5
~ Labeling of Special Nuclear Matsrlal,,,.......,........
43 1
4.1.6 Posting of Special Nuclear Material Locations..,........... 3 4.1.7 '
Confirmation of Analysis Assumptions,,...,,.............
4-4 y
4.2 Technical Practices...................................
44 l
L 4.2.1 Double Contingency Policy...,,,,.......,,...........
4-4
- 4.2.2
' Umits on Maximum Multiplication Factors,.........,,.....
4-4 4.2.3
. Geom etry.........................................
45 4.2.4 Neutron Absorbers..................................
45
)
4.2.5 -
- Concentration Control..............,,...............
45 M,
4.2.6 -
Multi Unit Arrays....................................
4-7 4.2.7 Criticality Safety Parameters,,.,,,........,,...........-
4-7 4.2.8 Sources of Criticality Data and Analytical Techniques........
4-9 L
t
[
CHAPTER 5 ENVIRONMENTAL PROTECTION p
5.1 Effluent Control.....................................
5-1 i
5.1.1 Gaseous Effluent Controls.............................
5-1 1
5.1.2 Uquid Effluent Controls................................
5-2 5.1.3 Process Chemical Waste Storage Lagoon System..........,
5-4 g
5.2 Environmental Monitoring................,............
5-5 4
5.2.1-Surface Sampling...................................
5-5 L
5.2.2 Groundwater Sampling............,,.,,.....
5.......
L, 5.2.3
- Sanitary Sewer Sludge Sampling........................
5-6
?L
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AMENDMENT APS'UCAf TON DATE.
PAGE NO -
ANF 3830.051 (6/89)
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ADuMCEDNUCLEARRELS CORPORATION-g p.g
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- SPECIAL NUCLEAR MATERIAL LICENSE NO. SNM 1227, NRC DOCKET NO. 701257-u
~
TABLE OF CONTENTS REV.
26' l
i CHAPTER 6 SPECIAL PROGRAMS
.P,aqq
.j 6.1 Proprietary Information...............................
6-1
,1 6.2 Occupational Safety.........................,........
61 6.3 Emergency Utilities........,......,.................. -
6-1 6.3.1 '
Emergency Electrical Power Supply,,,..,.............,
6-1 6.3.2
' Emergency Backup Water Supply.......................
6-2 6.4
. Radioactive Waste Management.........................
6-2
'l 6.4.1 Uq uid Wastes.... _.................................
6-2 l
6.4.2 Solid Raoloactive Waste..............................
6-2 6.5.
U F. Cylinde rs.......................................
6 i CHAPTER 7 - DECOMMISSIONING PLAN 4
7,1.
Decommissioning Criteria.............................
71 7.1.1-Uncontaminated Facilities.....................,.......
7-1 7.1.2 -
Residual Radiation Levels..........,,.................
71-7.1.3 '
Records............... '............................
71 7.1.4 Future Changes.....................................
71
=
7.1,5 -
Financial Provisions.........................,....,...
71 7.2 General Assumptions.................................
7-1 7.3 Proced u res........................................
7-2 L7.3.1
' U O, Building.......................................
722 7.3.2 -
Specialty Fuels (SF) Building....,..
73 J
7.3.3 Ancillary Facilities...................................
7-4 g
7.3.4 -
Waste Water Lagoons............,....................
74
.7.4 Cost E s ti m ate...................,.................,
75
- 7.5 Financial Assurance.................................,
75
' AP P E N DIX A.......................................
77
'l CHAPTER 8 - RADIOLOGICAL CONTINGENCY PLAN,.................
81
.i 1) i -
AMENOMENT APPUCATION DATE.
PAGE NO.:
ANF 3830.051 (G'89)
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. t' ADVANCEUNUCLEARMELS CORPORATICN gu p.2 SPECIAL NUCLEAR MATERIAL LICENSE NO. SNM 1227, NRC DOCKET NO. 701257 q
TABLE OF CONTENTS REV.
.l 26
-PART 11 SAFETY DEMONSTRATION P892 CHAPTER 9 - GENERAL INFORMATION q
9.1 Corporate Information.................................
9 l-l 9.2 Financial Qualification................................
91 a
9.3 -
Summary of Operating Objective and Process..............-
9-1!
j 9.3.1 G e n e r al.............................................
9-1
-9.3.2 Summary Process Description..........................
9-2 l>;
'9.3.3 Uranium Scrap Reprocessing..........................
9-3
.l l-9.3.4 Process Changes Since Last Ucense Renewal............
9-3
- l l=
9.4 Site Description......................................
9-4
~l 9.5 Location of Buildings On-Site...........................
9-5 1
' 9.6 Maps and Plot Plans....................... <.........
9-5 9.7 Ucense History......................................
95
< AP PE N D IX A.......................................
9-12
.l l
. CHAPTER 10 FACluTY DESCRIPTION H
I L
10.1 Plant Layout.......................................
101 10.1.1 SF Building Description............,..................
10 1 L
10.1.2:
UO, Building Description -,,.,,.........................
10-3 q
l
- 10.1.3 ;
ELO Building Description....................,,,.....
10-6
.l l
10.1.4:
Contaminated. Clothing Laundry...................,,....
10-6 j
' 10.1.5 =
. Fuels Storage Warehouse.........,,..,...... -.....,...
10 '?
- 10.1.6
. Radioactive Material Warehouse.........................
10-7 10.1.71 Fuel Cooling Test Facility (FCTF)........................
10-8 l
' 10.1.8 -
UF, Receiving and Storage Facility......,,..............
10-8 10.2 Utilities and Support Systems...................,.....
10-9 l'
10.2.1-Electrical Power.....................................
10-9 xl 10.2.2 Compressed Air System...............,..............
10 13
~
10.2.3
. Water............................................
10-13 1
10.2.4
- Sewer Sys tem......................................
10-14
,10.2.5 Gas and Chemical Storage,..........................
10-15 p
10.2.6 Communications and Annunciations.....................
1015 j
l 10.2.7-Breathing Alr.......................................
10-16 L>
-10.3 Heating, Ventilation, and Air Conditioning (HVAC).....,,... 10-17 l.
10.3.1 C rite ria...........................................
10-17 L
10.3.2 SC Building HVAC Systems...........................
10-18 L
10.3.3 UO, Building (North) HVAC Systems.....................
10-23 10.3.4 UO, Building HVAC Systems (South Addition) 10-27 AMENDMENT APPUCATION DATE.
PAGE NO:
ANF&,A051 (6/89)
,f,
. O,9 3
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1 ADitANCED NUCLEAR MRLB CORPORATION -
ap.g
)
j SPECIAL NUCLEAR MATERIAL LICENSE No. SNM.1227, NRC DOCKET NO. 701257
? TABLE OF CONTENTS REv.
26 CHAPTER 10 FACILITY DESCRIPTION (Cont.d)
PBQR i
10.3.5-
. UO, Building Une 2 Conversion HVAC Systerns............
10-30 10.3.6 U,0, Facility HVAC Systems...........................
10-33:
10.3.7 ELO Building HVAC Systems....... -,,,.................
10 35' 10.3.8 ELO Addition HVAC Systems...........................
10-37 i
10.3.9 Contaminated Clothing Laundry HVAC System...,........ 10-39 10.4 Radioactive Waste Handling...........................
10-40 J
10.4.1 Lagoon System Description............,,............. 10-41 p
10.4.2 Ammonia Recovery Description...... c,............... -..
10-43 p
10.4.3
. Lagoon Uranium Recovery Facility Description............,,
10-45
'10.4.4 Solids Uranium Recovery Facility........................ 10-46 10.4.5 Solid Waste Uranium Recovery Facility Description.......... 10-47 10.4.6 Plutonium Contaminated Waste Storage..................
10-50 D
10.5 Fire Protection.......................................10-50a 1'
10.5,1 Building Codes and Standards..........................10-50a 10.5.2 Fire Protection Uability inspections.....................10-50a 10.5.3 Fire Protection Program.......,,...................10-50b f
AP P E N DIX A...................................... 85 CHAPTER 11 ORGANIZATION AND PERSONNEL 1
11.1 Organizational Responsibilities...,,,.. '....,............
11-1 11.2 Functions of Key Personnel '.............................
11-1 11.3 Education and Experience of Key Personnel...............
11-1 11.3.1
- President and Chief Executive Officer - R. B. Stephenson.....
11 2 11.3.2
. Vice President,' Operations Division R. G. Frain............ 4 11.3.3 Manager, Manufacturing Engineering B. N. Femreite..,..,,.
11 5-11.3.4 Manager, Process Engineering - R. B. McLees..
11...........
= 11.3.5 Manager, Plant Engineering - J. W. Helton......,..........
11-8
' 11.3.6.-
Manager, Plant Operations - R. L. Feuerbacher.............
11-10 11.3.7.
Manager, Quality Control - D. J Hill......................
11-12
('
-11.3.8
- Manager, Materials and Scheaviing
- 1. J. Samaritano........ '11-14 11.3.9 Manager, Operations Planning and Scheduling D. C. Lehfeldt.
11-16 r
11.3.10-Manager, Safety, Security, and Ucensing - W. E. Stavig......
11-18 11.3.11 Supervisor, Safety - T. C. Probasco....................
11 20 4
,1 11.3.12 Criticality Safety Specialist - L D. Gerrald..................
11 21 11.3.13-Health Physics Specialist - J. E. Pieper................... 11-22 11.3.14 Radiological Safety Specialist E. L. Foster.
11-24 11.3.15 Health Physics Technician - E. S. Arel.............
11-26 11.3.16 Health Physics Technician D. L. Belt.................... 11-27 11.3.17 Health Physics Technician - L. G. Bradley 11-29 11.3.10. Health Physics Technician - J. D. Cudmore....
11-30.
l AMENDMENT APPUCATION DATE:
PAGE NOc ANF 3830.051 (6/89)
v 3
l ADMANCEDNUCLRARPUELS CORPORATION g p.2
' SPECIAL NUCLEAR MATERIAL LICENSE NO.' SNM 1227, NRC DOCKET NO. 701257 '
TABLE OF CONTENTS REY.
26 CHAPTER 11 ORGANIZATION AND PERSONNEL (Cont.d)'
Eagg 11.3.19
. Health Physics Technician - D. A. Marlin..................
11 32 11.3.20!
Health Physics Technician _ P. A. McBride.................
11 34 11.3.21-Health Physics Technician J. D. Nelson...................
11 35 11.3.22 Health Physics Technician.- J. A. Rosscup................ 11 37
- 11.3.23. Health Physics Technician - W. W. Smith..................
11-38 11.3.24 Health Physics Technician G. A. York................... 11 39 11.3.25 Manager, Regulatory Compliance - C. W. Malody, Jr.........
11 40 11.3.26 Staff Specialist Safeguards - J. B. Edgar..............*....
11-42 11.3.27 Industrial Regulations Specialist S. R. Lockhaven...........
11-44
-11.3.28. Vice President, Engineering Division _- T. A. Bjornard.........
11'45.
11.3.29-Manager, Research and Product Development G. L Ritter....
11-47:
11.3.30 Manager, Chemical and Ceramic Development 1. J. Urza.....
11-49 11.3.31-Manager, Materials Research - R. A. Busch,.......,......
11 51 11.4 Operating Procedures................................
11-52
.11.5 Training.........
11 52 11.5.1 Initial Training...
.................................._1152 11.5.2 Followup Training................................... 11-53 11.5.3 Emergency Response Training,,.......................
11 53
-11.6 Changes in Procedures, Facilities and Equipment.......
11 53 11.6.1 Facility and Equipment Changes........................
11 53 11.6.2.
R evi ew..,................. -.......................
11 54 11.6.3 Control / Documentation...............................
11-55 11.6.4 Review / Concurrence / Approval................,,........
11-55.
11.6.5 Execution.........................................
11 55 11.6.6 Acceptan ce........................................
11 55
-11.6.7 Rec o r d s..........................................
11 56 11.6.8 Procedure Changes..................................
11-56 CHAPTER.12 - RADIATION PROTECTION 12.1 P rog r a m..........................................
.12-1 12.2 Posting and Labeling.................................
12-1 12.3 External Radiation - Personnel Monitoring........
12 1 12.4
. Radiation Surveys....................,..............
12-3 12.5 Reports and Records..............................
12-3 12.6-Instru m e nts.....................................
12 4 12.7 Protective Clothing.............................
12-5 12.8 Administrative Control Levels (Including Effluent Control) 12-5 12.8.1 Occupational Exposure (Internal and Extemal)..
12-5 12.8.2
- Airborne Activity..,,...................
12-6 12.8.3 Uquid Activity (Effluent Monitors)......................
12-6 AMENOMENT APPUCAtlON DATE.
PAGE NOa i
ANF-3830.051 (6/89)
- _ _. _ =
3 AD68MCED 9NJCLEAR M)ELS CORPORATION; gn7 2 ;
SPECIAL NUCLEAR MATERIAL ~ LICENSE NO. SNM 1227, NRC DOCKET NO. 701257 TABLE OF CONTENTS REv;
.26 CHAPTER 12 - RADIATION PROTECTION (Cont.d).
Eagg
-12.9 Respiratory Protection.................................
12-6 12.10 Occupational Exposure Analysis........................
12-8
.12.11 Measures Taken to implement ALARA...................
12-8
'12.12 Bioassay Program...................................
12-9
-12.13
. Air Sampling and internal Exposure Program............... 12-10 12.14 Surface Contamination...........,,...................
12-11 Q
AP P E N D IX 'A c.. =..................................... 12-15 CHAPTER 13 - ENVIRONMENTAL SAFETY - RADIOLOGICAL AND NON-RADIOLOGICAL.
13.1 External Radiation...................................
13-1 13.2 Gaseous Effluents........................,,..........
13 1 13.3
' Uquid Effluents......................................
13-1 13.4
- Groundwater.......................................
13-2 13.5 Field Sampling......................................
13-2
= CHAPTER 14 NUCLEAR CRITICALITY SAFETY 14.1 Administrative Practices.......,................
14-1 14.2
. Equipment Design Criteria.............................
14 2 14.3 Basic Assumptions..................................
14-2 14.3.1-Accident Conditions................................,
14-2 14.3.2-K,,, Calculatio n......................................
1.43 14.3.3-
' S NM Properties....................................,
14-5 14.3.4
- Administrative Control Models..........................
14-9 14.4 Fixed Poisons..............................., =...... 14-11 l 14.5 Structural Integrity Policy and Review Program.............
14-11 14.6 Methods Validation.................................. 14-11
. - 14E.1 '
Well-Moderated Homogeneous Systems..................
14-12 14.6.2 Undermoderated Homogeneous Systerhs.................
14 12 14.6.3 Heterogeneous Systems.............................. 14-12 14.7 Refe re nces........................................
14-13 CHAPTER 15 - PROCESS DESCRIPTION AND SAFETY ANALYSIS 15.1 Reactions of Hydrocarbons with UF,.....................
15-1 15.2 Conversion of UF, to UO,.
15-2 15.2.1 Receipt and Storage of UF, hiinders....................
15-2 15.2.2 Vaporization........................
15-2
'15.2.3 Hydrolysis and Precipitation................
15-4 AMENOMENT APPUCATION DAf f.
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- SPECIAL NUCLEAR MATERIAL LICENSE NO. SNM 1227, NRC DOCKET NO. 701257 1
. l r
TABLE OF CONTENTS REY..
E 26 l
CHAPTER 15 PROCESS DESCRIPTION AND SAFETY ANALYSIS (Cont.d)-
,P, ggg -
1 4
'15.2.4
- Centrifugation, Drying and Calcination.....................
15-4 l
15.2.5 ~
Dry Conversion.....................................
15 1 15.2.6 Waste Handling......................................
15-5 1
15.3 Uranium Oxide Powder................................ 5 15.3.1 Powder Transport and Blending...........,....,.........
15-6;
- 15.3.2 '
Milling, Slugging and Granulation.......................
15-6
-15.3.3
~ Powder Storage.. -...................................
15 7 15.4 Pelletizing -..............,,............................
15-7.
0 15.4.1 Lubricant Blending...................................
15-7 L
15.4.2:
Pellet Pressing.......................................
15-8 15.4.3 Pellet Sintering.....................................
15-8 15.4.4' Pellet Grinding.......................................
15-8 15.4.5 Pellet Storage......................................
15-9 l
15.5
' Rod Fabrication..................................... 9
-b 15.5.1 Pellet Outgassing and Storage.........................
15-9 B'
15.5.2.
Rod Loading 1.........................................
15-9 15.5.3
' Rod Welding....................................... 15-10 15.5.4 Rod Leak Check.................................... 15-10 +
of
- 15.5.5 -
Rod Assay and X Ray................................
15 15.5.6 Rod Cleaning and Etching.....................
15-10 i
15.5.7
' Rod Autoclaving... -................................ 15-11 15.5.8 Final Rod inspection.........,..................
15-11 p'
E15.5.9 Final Rod Storage............................
15-11 15.5.10. Rod Downloading.......
15-11 F
'15.6 Neutron Absorber Fuel Rod Fabrication.........,,........
1512 l
15.7 Bundle Assembly....................................
15-13
(
L 15.7.1 Rod Picking and Assembly............................
15-13
,15.7.2 Inspection, Cleaning and Packaging.....................
1513 L
15.8.
Scrap Recovery.....................................
15 13 15.8.1 U 0 Facility..............,.........................
15-13 3
o
[
15.8.2 U N H Facility.......................................
15-14 m
15.8.3 Scrap Recovery Area.................................
15-14 j
15.8.4 Gadolinia Scrap. Recovery.....................
15 15 15.9 Temporary Storage.........................
15-15 CHAPTER 16 - ACCIDENT ANALYSES......................
16-1
!l' AMENDMENT APPLICATION DATE:
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1 TABLE OF CONTENTS
'^' -
(9d; UST OF TABLES 3
.- L l:
i 11,1 Specific Locations of Authorized Activities....,,............,,.
18 N
i l-3.1
. Radiation Safety Instrument Capabilities.,,.,,,,...,,,.-..,,,..
3-13 l-4.1.
- Safety Factors for Homogeneous Single Units.................
4 11 l7 - K 1-4.2 Safety Factors for Heterogeneous Single Units.................
4 12 l5,1 Stack ' Action Levels (Sample Stations).,,,.........,,.....
57 l 5.2
- Stack Action Levels (Location),,,,,....................,..
5-9
-j E
.119.1 Corporate Information.........,,............,,.....,......
9-6 4
l-10.1; ' Ammonia Recovery Major Equipment.......................
10 '
- Il 10.2.
LUR Process Equipment.......... -,..,........ -,,......... 10-52
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n' auenoutur appucariou car'
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July 25,1990 x
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ANF 3830.051 (6,'89) pp; m.
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S, ADVANCED NUCLEAR FtJELS CORPORATION mpg tSPECIAL NUCLEAR MATERIAL LICENSE NO. SNM 1227, NRC DOCKET NO. 701257 TABLE OF CONTENTS' REV.
-26 LIST OF FIGURES Flaure Paae-l2,1 Organization Chart......................................
2 19 12.2 Organization Chart - Safety, Security, & Ucensing...............
2-20 7'
l-2.3 Approval and Responsibility Matrix.,.......................
2 21 f,
I5.1 Field Sample Station Locations..............,,.............
5-10 f
4 l 5.2 Lagoon Test Well Locations...............................
5-11 mm ll-9.1 Organization Chart.,....................................
9-7 ll-9.2 Richland Area and Advanced Nuclear Fuels Plant............,,.
9-8 i
11-9. 3 Land Use Within 50-Mile Radius of ANF Site - Recreation.......,.
9 '
119.4 Land Use Within 50-Mile Radius of ANF Sits - Agriculture.........
9-10 11 9. 5 Land M 'Nithin 50-Mile Radius of ANF Site - Urban,,,.,,.......
9-11 2
. 11-1 0. 1 Plant Equipment Layout Site Plan..........................
10-53 11-1 0. 2
' Plant Equipment Layout Specialty Fuels Building...............
10-54 11-1 0. 3
- Plant Equipment Layout UO, Building....,,.................
10-55 Il-10.4 '.Piant Equipment Laycut UO, Building....,,....,,...........
10-56 m
-1110.5 Plant Equipment Layout UO, Building.......,,.,,,...........
10-57 ll 10.6 Plant Equipment Layout UO, Building..................,,..
10-58
+
1110,7 Plant Equipment Layout UO, Building,,.......,.....
10-59.
ll-10.8 --
Plant Equipment Layout UO, Building,.......................
10-60 11 10.9 ~-
Plant Equipment Layout Site Plan.,,,,..,,,...............
1 0-61 ll 10.10 Plant Equipment Layout Specialty Fuels Building....,,........
10-62 1110.11 Plant Equipment Layout UO, Building........................
10-63 L il-10.12. Plant Equipment Layout UO, Building.......................
10-64 1110.13-Plant Equipment Layout UO, Building.,,.....................
10-65 L 10.14 L Plant Equipment Layout UO, Building.......................,
10-66 p
' ll-10.15 ' Plant Equipment Layout UO, Building.......................
10-67 L
.ll 10.16 Plant Equipment !.ayout UO, Building...,,...................
10-68
' l! 10.17 Plant Equipment Layout ELO Building........................
10-69 Il 10.18 Advanced Nuclear Fuels Site Plan, Richland, WA..........
10-70 L
1110.19' Simplified Schematic HVAC System - SF Building SWUR Facility....
10-71 p
ll 10.20 ' Simplified Schematic HVAC System SF Building Production Facility 10-72 p
Il-10.21 Simplified Schematic HVAC System - Original UO, Building........
10-73 R
1110.22-Simplified Schematic HVAC System UO, Building Une ll Conversion Area.....................................
10-74
~
11-10.23 Simplified Schematic HVAC System - Main (South) Addition..
10-75 Simplified S:: hematic HVAC System - U 0, Facility.......
10-76 1110.24 3
AMENOMENT APPUCATION DATE.
PAGE NO.:
ANF 3830.051 (6/89)
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.i ADifANCED ARbCLEAR MELS CORPORATION gnp,2 SPECIAL NUCLEAR MATERIAL LICENSE NO. SNM 1227, NRC DOCKET NO.' 701257 TABLE OF CONTENTS
' REV.
1 26 LIST OF FIGURES (Cont.d) -
f.!QEt
.P__agg a
i ll 10.25 Simpitfied Schematic HVAC System - ELO Building.............
10-77 ll-10.26 Simplified Schematic HVAC System - ELO Building Addition.......
10-78' ll 10.27 Simplified Schematic HVAC System - Contaminated Clothing Laundry -
F acility..... -. -...... _.........,........................,
10-79 1110.28 Ammonia Recovery Waste Management Facility Equipment
. Arrangement.........................................
10-80 ll 10.29.: Ammonia Recovery Waste Management Facility Enqineering Flow y
=
l Diagram..............................
10-81 i
~
.11-10.30i Lagoon Uranium Recovery Production Facility - Eqspqent Arrangeme nt............................................
10-82.
I ll 10.31 Engineering Flow Diagram Lagoon Uranium Recovery Production ll F a cility................................................
10-83 l'
11-10.32-Fire Alarm _ System Site Plan, Drawing Ust, and Building Plans......
10-84
\\
i a
l-l l
l.
2 I
1' I -
r l:
1.
AMENDMENT APPtl CATION DATE.
P..GE NO :
ANF--3830.051 (&'89) en..
.v
f
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ADMANC8D NUCLE'AR FUELS CORPORATION l
y 7,2 SPECIAL NUCLEAR MATERIAL-LICENSE NO. SNM.1227, NRC DOCKET NO. 701257 r
PART I LICENSE CONDmONS REV.
26
. CHAPTER 2 ORGANIZATION AND ADMINISTRATION 1
The President of Advanced Nuclear Fuels Corporation has the ultimato responsibility for ensuring that all Company operations are conducted safely, and in full compliance with applicable Federal, State and local regulations, licenses, and permits.
All functions, which handle or store special nuclear material authorized by this -
Ucense, reside within two divisions of the Company, Operations and Engir.eering. The
- relationship of those segments of the organization which contain a significant safety or licensing responsibility is depicted in Figure 12.1. The organization c? the Safety, Security, and Ucensing Department which contains the responsible safety specialists and professionals is depicted in Figure.l-2.2.-
2.1 Oraanizational Responsibilities and Authority 2.1.1 President and Chief Executive Officer In connection with his ultimate safety responsibility, the President shall assure that adequate manpower, funding, and resources are made available within the Company to achieve the capabilities committed in,this Application. Additionally, he is responsible for assuring that there is a sound, consistent safety philosophy throughout the Company.
2.1.2 Vice President. Operations Division 4
The Vice President, Operations Division, is responsible for the overall management of the fabrication of nuclear fuels. He carries the responsibilities of the Senior. Site Representative. With this responsibility are the safety-related functions of operations,
- maintenance, plant support engineering, transportation, materials handling and storage, licensing and industrial, radiological and nuclear safety.
2.1.0 Manecer. Manufacturina Enaineerina The Manager, Manufacturing Engineering,ls responsible for all plant maintenance -
activities and for engineering assistance for all process, utility and safety systems. This
. position reports directly to the Vice President, Operations Division, and discharges day-to-zday responsibilities through the Manager, Plant Engineering, and Manager, Process Engineering.' He has the full authority to discharge his responsibilities for fumishing direct maintenance and engineering support to all plant activities.
]
2.1.4 Manaaer. Process Enaineerina Process engineering activities are directed by the Manager, Process Engineering, who reports to the Manager, Manufacturing Engineering.
wenouent amicanon oart:
July 25,1990 21 ANF.3830.051 (6/89)
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ADVANCEDNUCLEARMJELSCORPORATDN m p.7 y
i SPECIAL NUCLEAR MATERIAL LICENSE NO. SNM 1227, NRC DOCKET NO. 701257 r
PART I LICENSE CONDITIONS REV.
26 The Manager, Process Engineering, is responsible for providing process engineering support to the fuel fabrication plant. This includes the preparation of process parameter operating limits and process specifications. He provides technical support for welding operations and for developing improved welding methods. These activities are conducted within licensing and safety requirements. He has the necessary authority to carry out the responsibilities of this position.
2.1.5 Manager. Plant Enaineering N
The Manager, Plant Engineering, is responsible for all plant maintenance activities 3
and the necessary associated engineering support. This position reports directly to the Manager, Manufacturing Engineering.
in addition to common maintenance activities, the Manager, Plant Engineering, is responsible _ for establishing and conducting preventative maintenance and Inspection programs'for all safety-related equipmertt and systems, and for alerting the plant management of deteriorating and/or substandard conditions of safety related equipment
- and systems.
. He is responsible for maintaining and calibrating radiation protection Instruments l
and equipment, the criticality accident alarm system, and the fire detection and alarm i
system in accordance with established programs.- He is also responsible for establishing L
. and conducting tests of safety and emergency related equipment as required by
~
established programs.
The Manager, Plant Engineering, is also, responsible for the design and/or l
modification of new and existing equipment and facilities.'~This includes equipment and p
systems installed to maintain personnel exposures to radiation and radioactive materials, j'
as well as releases of radioactive materials to the environment, as low as is reasonably b
achievable, I
l 2.1.6L Manaaer. Plant Operations
- The operation of the fuel manufacturing facilities are directed by the Manager, Plant Operations, who reports to the Vice President, Operations Division.
The safe operation and control of plant activities, including the safety of the
- environs as influenced by the conducted activities, are the responsibility of the Manager, Plant: Operations.
Other responsibilities include preparation of detailed operating procedures,: training of employees, special nuclear materials safeguards control, membership in the Emergency Cadre, and membership in the ALARA Committee, i
auenoueur amcarou oare:
July 25,1990 2-2 b
l ANF 3830.051 (6/89)
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SPECIAL NUCLEAR MATERIAL LICENSE NO. SNM.1227, NRC DOCKET NO. 701257 PART I LICENSE CONDITIONS
-REV.
26 i
The Manager, Plant Operations, has the full authority required to discharge his responsibilities for safe operation of his plant.
l 2.1,71 Manager. Quality Control The Manager, Quality Control, reports to the Vice President, Operations Division,
- and is responsible for monitoring product quality during the manufacturing process as well as approving the quality of the finished product.~ This responsibility is discharge in part by having personnel directly involved as the manufacturing process progresses and i
in part by laboratory testing of process mntrol samples. This position has the full
- authority necessary to carry out the responsloilities.
2.1.8-Manager. Operations Planning and Scheduling The nuclear material traffic activities for ANF Richland facilities are directed by the Mantger, Operations Planning and Schaduling, who reports to the Manager, Materials
_ and Scheduling.
The responsibilities of the Manager, Operations Planning and Scheduling, include.
_1
. shipping,, receiving, and warehousing of nuclear materials, maintaining nuclear material
.{
transfer records, and assuring that plant inventories of nuclear materials do not exceed s
g authorized possession limits.
These activities are conducted within the confines of Ilcensing and safety requirements.
2.1.9 Manaaer. Safety. Security. and Licensina The Manager, Safety, Security, and Ucensing, reports to the Vice President,-
3 Operations Division, and is responsible for developing, administering, and auditing the
=
-licensing, health physics, criticality safety, environmental surveillance, Al. ARA, security, and safeguards programs for all Advanced Nuclear Fuels facilities located at Richland,.
The Manager, Safety, Security, and Ucensing, is wholly Independent with no a
-manufacturing responsibility, and has direct access to the upper management of the Company.
If the Manager, Safety, Security, and Ucensing, judges any operation as unsafe, he has the authority to request management to shutdown the affected operation. In the event of disagreement between line management and the Manager, Safety, Security, and AMENOMENT APRICAtlON DATE:
PAGE NO -
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ADMANCEDNUCLEARFinEACORPORATION mp.g 4
~ SPECIAL NUCLEAR MATERIAL LICENSE NO. SNM 1227, NRC DOCKET NO. 701257 PARTI UCENSE CONDITIONS REv.
26 Licensing, the operation shall be immediately shutdown, and the issue promptly brought to the attention of thw Vice President, Operations Division. Actions following from this authority are subject to review and approval solely by the President of the Company, 2.1.10 Supervisor. Safety The Supervisor, Safety, who reports to the Manager, Safety, Security, and Licensing, directs the acJvities of industrial safety, criticality safety, and radiological safety 3
personnel in conformanue with approved Company policies and programs in direct support of plant operations, t
if the Supervisor, Safety, judges any operation as unsafe, he has the authority to request management to shutdown the affected operation. In the event of disagreement between line management and the Supervisor, Safety, the opera 3ns shall be !mmeolately shutdown, and the issue promptly brought to the attention of the cognizant vapartment manager.
)
2.1.11 Criticality Safety Component There is a Criticality Safety Component within the Safety organization.
0 The responsibilities of the Criticality Safety Component include the following:
1.
Providing technical bases, critoria, and methods related to nuclear criticality dety.
I 2.
Preparing the Nuclear Csicality Pr.fsics Methodology Manual.
L i
3.
Providing criticality safeiy determinations for designs and procedures, j-including second party reviews.
1
}.
4.
Providing professional advice and counsel concerning matters within his u
cognizance.
1 5.
Membership in the Emergency Cadre, iy 6.
Performing compliance Inspections.
os.
Wi 7.
Approving Criticality Safety Specifications and Umit Cards.
L-1-
All determinations concernini, nuclear criticality safety shall be reviewed by a u
Second Party Reviewer who shall be knowledgeable in the technical data and qualified in the techniques of crit!cality physics. Second party reviews shall be arranged by the l-AMENDMENT APPL,CAtlON DATE PAGE NO:
ANF 3830.051 (G'89)
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ADHANCEDNUCLEARMRLSCORPORATION gup.2 SPECIAL NUCLEAR MATERIAL LICENSE NO. SNM 1227, NRC DOCKET NO.101267
{
PART I. LICENSE CONDITIONS REv.
26 L
Criticality Safety Component, and may be either from within the component or by an I
outside reviewer.
All nuclear criticality safety calculations and reviews shall be documented, and documents shall be held in permanent Company records. Calculational details, work sheets, etc., shall be held for a minimum period of six months following termination of the process or operation reviewed.
2.1.12 Health Physics Component There is a Health Physics Component within the Radiological Safety organization.
The responsibilities of the Health Physics Component include the following:
1.
Providing technical bases, criteria, and methods related to health physics, j
2.
Providing for outside sources for aid and special services related to health i
physics and emergencies.
)
L 3.
Performing compliance inspections.
1 h,
4.
Membership in the Emergency Cadre.
5.
Membership in the Al. ARA Committee.
6.
Approving exceptions to whole body exposure limits, if required,md justified.
i 7.
Reviewing Radiation Work Procedures.
i 8.
Providing professional advice and counsel concerning matters within his cognizance.
i 2.1.13 Pladiclogical Safety Component The general function of the Radiological Safety Component is to provide information, advice, and assistance tc me operating and engineering components such that personnel and environmental protection are maximized, and to keep adequate records to properly document conditions. Specific responsibilities of the Radiological l
Safety Component include the following:
1.
Adniinistering the plant radiological safet/ programs, and directing the activities of the Health Physics Technicians, July 25,1990 25 ANF.3830.051 (6/89)
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ADHSNCEDNUCLEAMMEL6 CORPORATION gy2 SPECIAL NUCLEAR MATERIAL LICENSE NO. SNM 1227, NRC DOCKET NO. 701257 PARTI LICENSE CONDITIONS REV.
26 2.
Establishing radiological safety programs in accordance with criteria and i
standards provided by the Manager, Regulatory Compliance.
Such j
programs include air sampling, contamination and radiation surveys, bioassay in vivo examination, and associated records systems.
3.
Reviewing established programs and evaluating effectiveness.
]
4.
Providing radiological safety analysis of proposed operational changes or modifications.
5.
Preparing Radiation Work Procedures.
l 6.
Assisting in preparation of reports to regulatory agencies.
j 1
7.
Auditing operations for compliance with regulatory criteria, license i
conditions, and Advanced Nuclear Fuels criteria.
J 8.
Assisting in health physics and radiation safety training.
l 9.
Membership in the Emergency Cadre.
10.
Membership in the ALARA Committee.
{
2.1.14 Health Physic, Technicians The collection and accumulation of basic radiological data, along with pre ciding routine radiation monitoring services, is conducted by Health Physics Technicians who l-report to the Supervisor, Safety. Senior Health Physics Technicians may be assigned mpwelal duties, along with appropriate titles.
Health Physics Technicians carry out established programs, and assist in initiating new or necessary progiudis; specific responsibilities shall include the following:
1.
Providing radiation monitoring.
2.
Collecting alt and effluent samples.
3.
Issuing and controlling personnel dasimeters.
t 4.
Maintaining all records pertain!.ig to personnel exposure, contamination and air surveys, sampling, ir.spections, tests, etc.
aventwtuta m ca m w oara July 25,1990 2-6 ANF.3830.051 (6/89)
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ADMHll8DMJCLEARMBER CORPORATION gup.2 SPECIAL NUCLEAR MATERIAL LICENSE NO. SNM.1227, NRC DOCKET NO. 701257 PARTI UCENSE CONDITIONS REV.
26 5.
Inspecting operations and reporting violations of written radiation protection procedures.
6.
Membership in the Emergency Crew.
7.
Providing personnel decontamination.
8.
Providing training in radiological safety, 2.1.15 Manager..Renulagv Comoli,d1GA The Manager, Regulatory Compilance, reports to the Manager, Safety, Security, and Ucensing, and is responsible for obtaining all licenses, permits, and amendments thereto necessary for plant operation that involve the safety of the workers, public, or environment. He is also responsible for the safeguards program. He is responsible for ensuring that alllicensing and permit requirements are appropriately implemented, and implementation adequately documented. This is accomplished through issuance of appropriate Company Policies and Standards, and by approval of certain implementing procedures. He is the Company interface with regulatory agencies, and will host audits by Regulatory Representatives and respond to any audit reports for the Company.
2.1.16 Vice President. Enoineerina Divialon The Vice President, Engineering Division, in part, is responsible for research and development activities in support of the fabrication of nucl ear fuels, including the condur,.
of certain demonstrations involving special nuclear materials.
2.1.17 Manager. Research and Product Development This position reports to the Vice President, Engineering Division, and is responsible fot esearch into new materiais, conducting fuel cooling flow stability testing, and new processes and equipment in support of long range product and process improvements.
2.1.18 Manager. Ma'nufacturina Technolony The Manager, Chemical and Ceramic Development, is responsible for process development activities for new and improved chemical ceramic processes for preparing UO, and for treating liquid and solid wastes. These activities arc conducted within licensing and safety requirements.
L.woutwi areucciou out' July 25,1990 27 ANF 3830.051 (6/89)
1 ADMANCSD ARbCLEAR FtELS CORPORATION mp.g SPECIAL NUCLEAR MATERIAL LICENSE NO. SNM 1227, NRC DOCKET NO. 701257 i
PART I UCENSE CONDITIONS REV.
26 2.1.19 Mananer. Materials Research The operation of the Engineering Laboratory Operations (ELO) facility is directed by the Manager, Materials Research, who reports to the Manager, Research and Product i
Development. '
The safe operation and control of facility activities, including the safety of the environs as influenced by the conducted activities, are the responsibility of the Manager, 1
Materials Research.
Other responsibilities include preparation of operating procedures, training, and supervision of all activities involving radioactive materials within the ELO facility.
The Manager, Materials Research, has the full authority required to discharge his j
responsibilities for safe operation of his facility.
2.1.20 Manaaer. Product Development and Testina The operation of the Fuel Cooling Test Facliity (FCTF) (where reactor simulated flow tests involving a single fuel element are conducted) is directed by the Manager, Product Development and Testing, who reports to the Manager, Research and Product i
Development.
The Manager, Product Development and Testing, is responsible for the safe
. operation of the FCTF within the constraints imposed by license conditions, Radiation Work Procedures, and Criticality Safety Specifications.
I 2.2 Personnel Education and Experience Reaulroments Responsibilities and authorities of all line managers shall be provided in writing.
Hiring of managers and key professionals in plant operations, health physics, and nuclear -
criticality safety shall be subject to approval by the Vice President, Operations Division.
.The Manager, Plant Operations, and managers in engineering and technical services functions which have responsibilities for the processing, storing, or handling of special nuclear materials, shall have a minimum of two years of experience in the nuclear industry, and a degree in Science or Engineering. There are certain other positions where a technical degree is not required; however in those cases, the incumbent will have adequate job training, and technical support and overview will be available. Specific requirements for key safety professionals whose major responsibility is in a safety field are listed below.
menow wt neeucmon oat July 25,1990 28 ANF 3830.051 (rvB9)
AD%MDEDNUCLEARRELS CORPORATION m p.2 SPECIAL NUCLEAR MATERIAL LICENSE NO. SNM.1227, NRC DOCKET NO. 701257 REv.
PART I. UCENSE CONDITIONS 26 2.2.1 Mananer. Safety. Security and Licensing The minimum qualifications of the Manager, Safety, Security, and Licensing, shall be a BS degree in a technical field with 10 years experience in 'ne nuclear energy field, of which four shall have been in positions with nuclear safety responsibility.
2.2.2 Mananer. Reaulatory Comollance The minimum qualification for the Manager, Regulatory Complie.nce, shall be a BA or BS degree in Science or Engineering, plus eight years experience in the nuclear field of which four years experience shall have been in positions with nuclear safety or radiological safety responsibility.
2.2.3 Supervisor. Safety The minimum qualifications shall be a BS degree in a technical field, with five years experience in radiation safety, or, in the absence of a degree, then 10 years experience shall be r_oquired.
2.2.4 Crtticality Safety Specialist The minimum qualifications of at least one member of the Criticality Safety Component, as well as for each Second Party Reviewer, shall be a BS degree in Science or Engineering with at least two years of experience in nuclear criticality safety analysis.
2.2.5 Health Physics Specialist The minimum qualifications of at least one member of the Health Physics Component shall be a BS degree in Science or Engineering with five years experience in radiatien protection, including at least two years of radiation protection experience allied with nuclear fuel fabrication.
2.2.6 Health Physics Technician The minimum qualifications of certified Health Physics Technicians shall be a high school diploma with two years of radiation monitoring experience, or four years of similar experience in lieu of a high school diploma. Health Physics Technicians shall complete a formal Advanced Nuclear Fuels training program, or shall have had equivalent prior training; they shall become proficient in Advanced Nuclear Fuels radiological safety programs, criteria, specifications, procedures, and routines.
autwout=v amcatou omie July 25,1990 2-9 ANF-3830.051 (6'89)
t j
ADuhNCED ARbCLEARMRLS CORPORATK.W gu p.y SPECIAL NUCLEAR MATERIAL LICENSE NO SNM 1227, NRC DOCKET NO. 701257 PART I LICENSE CONDmONS REv.
[
26 2.3 Safety Review Committees 2.3.1 HeaMh and Safety Council t.
Advanced Nuclear Fuels has established the Heahh and Safety Council which convenes monthly at Advanced Nuclear Fuels's fuel manufacturing plant in Richland' Washington, to review various aspects of the safety program, including:
1.
Industrial safety practices and trends.
2.
Radiological safety practices and trends.
3.
Criticality safety practices and trends.
i 4.
Adequacy of emergency planning and procedures (including results of tests and drills).
5.
Overall safety awareness and attitude of employees and programs for promoting improvements.
6.
Unusual occurrences and accident investigations, including i
recommendations to prevent recurrences.
7.
Status of Council related action items.
Membership of this Councilincludes:
Vice President, Operatior$s Division (Chairman). -
1.
2.
Supervisor, Safety (Secretary).
3.
Manager, Safety, Security, and Ucensing (Co-Chairman).
4.
Vice President, Operations Division, staff.
5.
Vice President, Engineering Division, and his staff.
~
6.
Appropriate managers within these and other organizations.
7.
Key safety engineers and specialists.
Designated members of the Council make monthly inspections of buildings and grounds for housekeeping and safety practices, and report the findings to the Council at July 25,1990 2-10 ANF.3830.051 (6'89)
ADMSNCEDMJCLEARMELS CORPORATION gnp.g SPECIAL NUCLEAR MATERIAL LICENSE NO. SNM.1227, NRC DOCKET NO. 701257 PARTl LICENSE CONDmONS REv.
26 the monthly meetings. Findings are assigned to individuals for resolution and are held open until resolved.
2.3.2 ALARA Committee An ALARA (6s Low As Bessonably 6chievable) Committee maintains awareness of trends in employee radiation exposure and radioactivity content of effluent releases.
The membership of the Committee includes:
1.
Manager, Regulatory Compliance (Chairman).
2.
Health Physics Specialist (Secretary).
3.
Supervisor, Safety.
4.
Manager, Plant Engineering.
5.
Manager, Safety, Security, and Ucensing, j
i 6.
Manager, Plant Operations, 7.
Manager, Procest Engineering.
The ALARA Committee shall conver,s at least saml-annually.
The ALARA 3
Committee shall issue a formal report at least annually to the Health and Safety Council reviewing employee exposures and effluent release data to determine:
1.
Trends in personnel exposures and effluents.
2.
If personnel exposures or radioactive effluents might be lowered under the concept of ALARA.
i 3.
If equipment for offiuent and exposure controlis properly designed, used, maintained, and inspected.
Their reports shall include review of required audits and inspections performed during the past year, and review of employee external exposures, bioassay results, unusual occurrences, effluent releases, in plant airborne radioactivity, and environmental monitoring.
2.4 Trainina
- uenoutwr Amcation oarc.
July 25,1990 2-11 ANF 3830.051 (6'89)
ADMANCEDMbCLEARNELS CORPORATON gn p.2 SPECIAL NUCLEAR MATERIAL LICENSE NO. ! NM 1227, NRC DOCKET No. 701257 REV.
PART l. fJCENSE CONDITIONS 26 in addition to normal on the job training, employees are instruct >d in radiation protection and criticality safety requirements and procedures, industrial safety, fire protection, and emergency procedures. The degree of training is commensurate with each employee's position in the Company (related to general and special responsibilities),
and with the extent of the employee's contact with radioactive and fissionable materials.
The minimum safety-related training requirements for various employee positions are established by the Safety, Security, and Uconsing Department, including training and retraining schedules and training course content. Employee instruction is provided by personnel knowledgeable in the various training topics. All formal training is documented, and records are maintained by the Safety, Security, and Ucensing Department.
2.4.1 initial TralDl09 Each employee is provided initial instruction adequate to allow him to safely start -
on the-job training; they are provided the full instruction within two weeks a*ter starting work. Prior to assignment to independent operation, each employee is required to have beta instructed in radiation protection, criticality safety, and emergency requirements and pocedures as appropriate to his position.
2.4.2 Followun_ Training When changes are made in radiation protection, criticality safety controls (procedures, specifications, etc.), or in emergency procedures, each employee affected is promptly informed and properly Instructed.
Safety topics are routinely discussed in monthly safety meetings. Additionally, each employee routinely working with special nuclear material receives annual refresher instruction as part of Advanced Nuclear Fueis continuing program k radiation protection and criticality safety awareness, The effectiveness of this annual i' fresher training is determined by giving the employees a written examination and re' owing the correct answers to the questions at the end of the test.
2 3 Health Physics Technician Trainina Health Physics Technicians are given special training related to their radiation protection assignment. Previous training is accepted if considered equivalent to the Advanced Nuclear Fuels training program. Despite previous acceptable training, the Health Physics Technicians are required to become proficient in Advanced Nuclear Fuels radiation protection and criticality safety programs, criteria, specifications, procedures, and routines, as demonstrated by successfully passing an Advanced Nuclear Fuels certification examination within six months after employment as a Health Physics Technician, in addition, refresher training is provided to all Health Physics Technicians
- annually, autwoutut amicanon ontc July 25,1990 2-12 ANF 3830.051 WB9)
AD696NCEDNUCLKARM,MA CORPORATION y
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SPECIAL NUCLEAR MATERIAL LICENSE NO. SNM 1227, NRC DOCKET No. 701257 PART I LICENSE CONDITIONS REV.
26 2.4.4 Training Evaluations Employee awareness of, and conformity to, safety requirements and procedures, as well as the effectiveness of safety tral:.ing programa, shall be evaluated at least monthly by the Radiological Safety Com Criticality Safety Component for criticaHty'ponent for radiation protection, and by the safety. These Advanced Nuclear Fuels staff members have the authority to require retraining of employees. These evaluations shall be documented along with actions required by them.
2.5 Operating Procedures. Standards and Guides Advanced Nuclear Fuels conducts its business in accordance with a system of Standard Operating Procedures, Company Standards, and Policy Guides. Advanced Nuclear Fuels is committed to controlling activities involving special nuclear materials in accordance with these approved written procedures, standards, and guides. These documents are prepared, reviewed, revised, approved, and implemented in accordance with the Approval and Responsibility Matrix (Figure 12.3). Plant and facility managers are
. responsible for assuring compliance with all pertinent radiation protection and criticality safety procedures, specifications, and practices within their respective facilities. Violations of radiation protection or criticality procedures, or specifications which are of repetitive or serious nature, are subject to discipt.iary action.
The Supervisori afety,is responsible for assuring that Health Physics Technician S
activities are conducted in accordance with established and approved procedures, methods, and frequencies.
2.6 Internal Audits and Inspections Audits and inspections are conducted to determine that plant operations are conducted in compliance with regulatory requirements, license conditions, and written procedures. These audits and Inspections apply to radiation protection, criticality safety,
. hazardous chemical safety, fire protection, and environmental protection.
2.6.1 Radiation Protection As part of their normal activities, the Supervisor, Safety, and Health Physics Technicians perform daily inspections as a part of their procedures for collecting air samples and performing radiation and contamination surveys of all areas of the plant where uncontained radioactive materials are stored, processed, or otherwise handled.
Detected Infractions of radiation protection procedures, exposure controls, and sound radiation protection practicet are corrected on-the spot as part of a continuing education effort in their field of expertise. Serious infractions and noncompliance with license aviwowm amication oato July 25,1990 2 13 ANF 3B30.0$13'89)
ADHMCEDNUCLEARMELSCORPORATCN w.y SPECIAL NUCLEAR MATERIAL LICENSE NO. SNM.1227, NRC DOCKET NO. 701257 I
PART l. UCENSE CONDITIONS REV.
26 i
conditions are documented and distributed to the respecave facility management, and to the Manager, Safety, Security, and Ucensing.
The Health Physics Component of Safety, Security, and Ucensing makes monthly
[
audits of radiation protection practices and exposure controls. These audits are made in accordance with a written plan. Results of these audits are documented, including any j
recommended corrective actions, and distributed to the respective facility management, and to the Manager, Safety, Security and Ucensing. 'the Health Physics Component shall followup on each detected discrepancy in subsequent audits until there is satisfactory resolution, i
2.6.2 Criticality Safety While performing their daily duties, Health Physics Technicians are alert for infract!ons of criticality safety specifications and limits.
Detected infractions are communicated to the Criticality Safety Component.
The Criticality Safety Component conducts monthly audits of the various criticality safety control systems. (e.g.,' moderation control, enrichment control, neutron absorber Inspections, process alarms, and trips related to criticality safety, etc.). The Criticality Safety Component also audits new installations and modifications to equipment and processes prior to their operation with special nuclear storial. These audits are performed in accordance with a written plan, and reports of the findings are submitted to the respective facility management, and to the Manager, Safety, Security, and Ucensing.
The Criticality Safety Component shall followup on each detected infraction in subsequent audits unt!l there is satisfactory resolution.
2.6.3 Hazardous Chemical Safety As part of their normal duties, the Supervisor, Safety, and the Industrial Hygiene Specialist make periodic inspections of all areas of the plant where hazardous chemicals are stored, processed, or otherwise handled. Detected discropancies of exposure controls, and sound industrial hyglene practices are corrected or ae-spot as part of their j
continuing educational effort.
The Industrial Hygiene Specialist also monitors the levels of the various chemicals that are present on our plant site in accordance with a written industrial Hygiene Monitoring Progfam Plan. Results of these inspections are documented, including any l
recommended corrective actions, and distributed to the respective facility management, and to the Manager, Safety, Security, and Ucensing. The industrial Hygiene Specialist shall followup on each detected discrepancy in subsequent inspections until there is l-satisfactory resolution.
l avenourut amication out.
July 25,1990 2-14 ANF 3830.051 (&89)
1 ADMANCEDNUCLEARMMLS CORPORATION g.g SPECIAL NUCLEAR MATERIAL LICENSE NO. SNM 1227, NRC DOCKET NO. 701257 PART l. UCENSE MNDmONS
- REV, 26 2.6.4 Fire Protection The inspection Comm;..ee of the Richland Health and Safety Council performs j
monthly insp>ctions of selected areas of the Richland facility. These inspections include housekeeping concerns, as well as industrial safety concerns. A facility with good housekeeping (combustible wastes property contained, emergency exits accessible and J
uncluttered, fire extinguishers property maintained), will experience fewer and less serious l
firos. Results of *hese inspections are documented, including any recommended corrective actions, and distributed to the respective facility menagement. The Incpection Committee shall followup on each detected discrepancy and recommended corrective action in subsequent inspections until there is satisfactory resolution.
The Safety Supervisor ensures that a monthly inspection is made of all plant fire l
extinguishers in accordance with a written plan. Results of these inspections are documented, and any detected discrepancies are corrected during the inspection, 2.6.5 Environmental Protection Inspections The Industrial Hygiene Specialist monitors the levels of regulaSd material released i
to the environment in accordance with a written plan. The Health Physics Technicians are responsible for the field sampling under the g"idance of t!'e Industrial Hygiene Specialist. Results of this monitoring are documented and distributed to the Manager, Safety, Security, and Ucons!ng.
The Health Physics Component makes monthly. inspections of environmental protection practices and exposure controls. These inspections are made in accordanco l
with a written plan.
Results _of these inspections are documented, including any recommended corrective actions, and distributed to the respective facility management, and to the Manager, Safety, Security, and Ucensing. The Health Physics Component shall followup on each detected discrepancy and recommended corrective action in i
subsequent inspections until there is satisfactory resolution.
2.7 investiastions and Reportina 9f Reportable incidents in addition to, and/or in line with, the reporting requirements specified in other sections of this Application, or in Regulatory Guide 10.1, the following reporting schedule is adhered to:
1.
Employee, former employee, or terminating employee radiation exposure information shall be reported to individuals in accordance with 10 CFR 19.13(b)(c)(e);
auewoutut *micatiow oate:
July 25,1990 2 15 ANF 3830.051 (W89)
s ADnl@C8DNUCLEARPERLBCORPORATDY ap.g SPECIAL NUCLEAR MATERIAL LICENSE NO. SNM 1227, NRC DOCKET NO. 701257 PART l. UCENSE CONDmONS REv.
26 2.'
Personnel exposure upon termination of employment or work shall be submitted to the NRC in accordance with 10 CFR 20.408(b) and 10 CFR 20 409; 3.
Employoe exposures and monitoring information shall be reported to the NRC in accordance with 10 CFR 20.407; 4.
Overexposures and excessive levels and concentrations shall be reported to the NRC in accordance with 10 CFR 20.405(a) and 10 CFR 20.409; 5.
The NRC shall be notified of incidents in accordance with 10 CFR 20.403(a)(b);
6.
Theft, or loss of licensed material, shall be reported in accordance with 10 CFR 20.402(a)(b)(c);
7.
Effluent monitoring Information shall be reported to the NRC in accordance with 10 CFR 70.59; 8,
in the event that the radioactivity in plant gaseous effluents exceeds 50 microcuries per calendar quarter, a report shall be submitted within 30 days to - the NRC (Director, Office of Nuclear Material Safety and Safeguards, with a copy to NRC Region V office of I&E), identifying the cause for exceeding this value, and the corrective actions to be taken to reduce release rates; 9.
If parameters important to dose assessment of the public relative to gaseous effluents from the plant change, a report shall be cubmitted to the NRC (Director, Office of Nuclear Material Safety and Safeguards, with a copy to NRC Region V Office of I&E) within 30 days identifying the changes in parameters, and proWding an estimate of the resultant change in dose commitment; 10.
Reports of excessive radioactivo contaminat6n on packages of radioactive material, and excessive radiation levels exiernal to the packages on recalot, shall be reported to the NRC immediately in accordance with 10 CHC 20.205(b)(2) and 10 CFR 20.205(c)(2);
11.
Accident reports on transportation of licensed material shall be reported to the NRC and DOT in accordance with 10 CFR 71.5(b) and 49 CFR 171.15 and 49 CFR 171.16.
July 25,1990 2 16 ANF-3830.051 (6'89) m
ADMShCSDhMCLEARMELS CORPORATION gu p.y SPECIAL NUCLEAR MATERIAL LICENSE NO. SNM 1227, NRC DOCKET NO. 701257 PARTI LICENSE CONDITIONS REV.
26 The Manager, Safety, Security, and Ucensing, has the responsibility for investigating, recording, reporting, and following up on actions taken for reportable incidents in accordance with NRC reporting requirements.
2.8 Secords j
in addition to, and/or in-Une with, the documentation requirements specified in other sections of this Application and 10 CFR 20.401, the following records are retained:
j 1.
Personnel radiation exposure histories and determinations of personnel accumulated dose. (Information on personnel prior radiation exposure histories is obtained in accordance with 10 CFR 20.102(c)(1).)
2.
Employee radiation exposures, external and intemal, including dose evaluations.
3.
Health Physics Technicians' radiation and contamination surveys, including 1
room air and exhaust air monitoring.
4.
Environmental surveitiance data and waste discharge reports.
5.
Incident invel,tigstion reports.
- t 6.
Employee indoctrination, training, and retraining reports, j
L 7.
Facility and process acceptance testo, l
L 8.
Radiation safety, health physics, and criticality safety inspection reports.
9.
Richland Health and Safety Council meeting reports.
10, ALARA Committee reports.
l 11.
Criticality dosimeter inspection reports.
12.
Reports of test results for the criticality accident alarm system.
l 13.
Reports of test results for the smergency electrical power supply system.
l l
14.
Radiation detection instrument maintenance and calibration; also for the neutron detectors of the criticality accident alarm system.
15.
Results of sealed source leak checks.
Turnowrut amcar,o= oate July 25,1990 2 17 ANF 3830.051 (6/89) m
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- REV, 26 16.
HVAC system monitoring and test results.
17.
Engineering Change Notices (ECN).
18.
Revisions to Nuclear Criticality Safety Anaysis.
Such records are maintained for a minimum period of five years, unless there are legal requirements for longer retention periods for specific records, i
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July 25,1190 2 18 ANF-3830.051 (G'89)
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PART ll. SAFETY DEMONSTRATION REV.
26 CHAPTER 9 GENERAL INFORMATION 9.1 Corporate information l
1 The names, addresses, and citizenship of the current principal officers of Advanced Nuclear Fuels are listed in Table ll-9.1. Advanced Nuclear Fuels is wholly.
owned by Siemens KWU, Inc., a Delawere Corporation which, in turn, is wholly owned by Siemens Corporation that is a wholly owned subsidlary of Siemens AG, a Federal l
Republic of Germany corporation.
The top organizational structure of Advanced Nuclear Fuels is depleted in Figure il 9.1. The President reports to the Board of D! rectors and directs all Company functions.
The handling, processing, and storage of special nuclear material, to which this license.
l applies, is under the direction of the Vice President, Operatiora Division, and Vice j
President, Engineering Division.
There are five departments within these two divisions which are involved in the j
handling and/or processing of special nuclear material. These ere Plant Operat!ons, L
Materials and Scheduling, Manufacturing Engineering, Quality Controi, snd Research and Product Development. Additional descriptive information on these orgenizations was presented in Chapter 2.
9.2 Financial Qualification A copy of the Annual Report for 1986 of Siemens AG is appended at the end of this chapter which describes the financial condition of the corporp!!ca with which Advanced Nuclear Fuels is affiliated.-
9.3 Summary of Operatina Obloctive and Process
)
9.3.1 General l
l The objective of activities covered by this license application is the production of low enriched uranium fuel for light water reactors. This is accomplished by beginning with UF, as a feedstock and incorporates processes ancillary to the main process including liquid waste treatment and disposal, scrap recovery and recycle, and combustible waste incineration and disposal. Plant capacity is nominally 700 metric tons
'per year. A very brief description of the mainline process is given below.
lo auenourut amicatow oat July 25,1990 9-1 l
ANF.3830.051 (6/89)
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AD9%h0C8DNUCLEARMELS CORPORATION gn p.2 SPECIAL NUCLEAR MATERIAL LICENSE NO. SNM.1227, NRC DOCKET NO. 701257 REv.
PART 11 SAFETY DEMONSTRATION 26 11.3.3 Manager. Manufacturing Engineerina S. N. Femreite Education BS Metallurgical Engineering -
1966 University of Idaho MS Metallurgical Engineering 1967 University of Idaho Post-Graduate MBA Studies 1974 University of Washington Experience 1967 1970 Employed by United Nuclear in Richland, Washington as a Senior Process Development Engineer responsible for manufacturing process and materials development for defense reactor fuels.
1970 Present Employed by Advanced Nuclear Fuels Corporation (Exxon Nuclear Company, Inc., prior to January 1,1987).
Senior Engineer, Research and Engineering, responsible for process development, materials evaluation, and process support for UO, and MOX commercial fuels.
Manager, Shop Operations, responsible for manufacturing operations for UO, and MOX fuels.
Manager, European Projects, responsible for planning, staffing, startup, and initial startup of the European Fuel Plant.
Manager, Uranium Waste Project, responsible for process development, design, installation, and startup of liquid and solid waste recovery systems in Richland manufacturing plant.
Manager, Richland Employee Relations, responsible for Human Resources function for Richland site.
Manager, Plant Operations, responsible for design criteria, staffing, training, and startup of manufacturing operations for a DOE plant at the Idaho National Engineering Laboratory.
Manager, Corporate Employee Relations, responsible for corporate Human
. Resources function in U.S. and Europe.
we a tuti m catenoAtt'
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July 25,1990 11 5 ANF 3830.051 (G'89)
7_a..
i ADMUIlCSD ARJCLEAR MELS CORPORATION m p.2 SPECIAL NUCLEAR MATERIAL LICENSE NO. SNM 1227, NRC DOCKET NO. 701257
.l
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PART 11 SAFETY DEMONSTRATION REV.
J 26 1
Manager, Operations-Richland, responsible for Manufacturing, Quality Control, and Maintenance for the Richland site.
j Manager, Manufacturing Engineering, responsible for Process and Plant Engineering for the Richland site.
J i
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SPECIAL NUCLEAR MATERIAL LICENSE NO. SNM 1227, NRC DOCKET NO. 701257 PART ll SAFETY DEMONSTRATION REv.
26 11.3.4 Manager. Process Engineerina. R. B. McLees l
Education BS Ceramic Engineering 1959 Clemson University MS Ceramic Engineering 1960 Clemson University 1960-1969 Empicyed by Y 12 Plant, Oak Ridge, Tennessee as a Development Engineer engaged in materials research and development.
1969 1975 i
Employed by General Electric, Wilmington, North Carolina as an Equipment Engineer responsible for equipment installation and startup.
1975-1976 Employed by General Atomic Plant, San Diego, California as a Staff Engineer responsible
. for the liaison with A/E on design of HTGR fuel fabrication plant.
1976-Present Employed by Advanced Nuclear Fuels Corporation (Exxon Nuclear Company, Irc., prior to January 1,1987),
Equipment Engineer. (19'i6-1977)
Supervisor, Chemical Conversion Operation. (19771978) f Lead Engineer, incremental Plant Expansions, (19781980) i Project Engineer,550 MTU Plant Expansion and Ungen Pelletizing Project. (1981-l 1985)
Manager, Process Support Engineering. (1985-Present)
July 25,1990 11 7 ANF.3830.051 (W89)
Le j
j ADMSNCEDNUCLEARMELSCORPORATOV y.g SPECIAL NUCLEAR MATERIAL LICENSE NO. SNM 1227, NRC DOCKET No. 701257 J
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PART 11. SAFETY DEMONSTRATION REV.
]
26 i
11.3.5' Manager. Plant Enoineerina J. W. Helton j
I Education
' BS Mechanical Engineering 1955 Colorado State University
-i
,1 MS Nuclear Engineering 1963 University of Washington.
J m
Professional Engineer Ucense State of Washington Experience 1955 -1970 l
' i" o
i Employed by General Electric Company in a variety of positions.
1.j Various engineering assignments in Richland, Washington, including reactor
+
operator training, inspection, piping design engineer, and engineering supervisor.
(1955 1985)
Ma' ager, Construction Engineering, responsible for admir,lstration of a
=)
+
n construction subcontractor involved in the construction completion, repairs, and alterations of the Saturn V Test Facility. (19651976)
Resident Manager, Monticello Nuclear Power Plant, site manager for construction of the Turkey Point plant.
1970 - Present Employed by Advanced Nuclear Fuels Corporation in a variety of positions in Richland, Washington.
l
~
' Manager,- Manufacturing Engineering, responsible for the determination,
+-
engineering, installation and maintenance of production equipment for the fuels y,
plant. (19701972) l Project Engineer responsible for project modifications and additions to facilities and process equipment for fuels plant. (19721975)
G Project Manager responsible for project design, licensing, construction, and
+
. startup of nuclear fuels plant in Ungen, W$est Germany. (19751978)
I i
+ -
Manager, Construction, responsible for all construction activities by construction
]
contractors during major plant additions and modifications. (19781982)
July 25,1990 11 8 wtwoue=1 ammen oate-ANF 3830.051 (6/89)
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SPECIAL NUCLEAR MATERIAL LICENSE NO. SNM 1227, NRC DOCKET NO. 701257 PARll SAFETY DEMONSTRATION REV.
26 Project Engineer responsible for project activities associated with facility and i
process equipment additions and/or modifications for fuels plant. (19821985)
Project Manager responsible for addition of pelletizing equipmerkt and facilities in the Ungen, West Germany fuels plant. (19851987) i Staff Engineer responsible for all construction activities for fuels plant. (1987 1990)
Manager, Plant Engineering, responsible for the engineering and maintenance of all process equipment, facilities, and facility equipment for Advanced Nuclear Fuels plant. (1990-Present) l i.
L
^ " ' " " ' " ' ' * * * " " ' ' ' '
July 25,1990 11-9 ANF-3830.051 (6/89)
,r ADMANCEDNUCLEARFERLS CORPORATION y.g SPECIAL NUCLEAR MATERIAL LICENSE NO. SNM 1227, NRC DOCKET NO. 701257 PART 11 SAFETY DEMONSTRATION REV.
26 11,3.8 Manager. Plant Operations R. L Feuerbacher Education BS Nuclear Engineering 1974 Oregon State University i
MS Nuclear Engineering 1984 University of Washington MBA Business Administration 1989 University of Washington Experience 1974 1975 Employed by General Atomic Company in two engineering positions in LaJolla, California.
Nuclear Engineer, Core Physics Section, performing fuel design and reactor core development for the high temperature gas cooled reactor. (1974)
Engineer, Fusion Engineering, performing structural and thermal hydraulic flow analyses for a Tokamak fusion test facility. (1975) 1975 Present Employed by Advanced Neelear Fuels Corporation (Exxon Nuclear Cornpany, Inc., prior to January 1,1987) in a variety of positions in Richland and Bellevue, Washington.
Nuclear Engineer, BWR Neutronics, performing fuel design and in-core fuel management for bolling water reactor (BWR) nuclear power plants. (19751977)
Nuclear Engineer, PWR Neutronics, performing fuel design and in core fuel
+
management for pressurlzed water reactor (PWR) nuclear power plants, including on-site support for power plant startups. (19771979)
Lead Engineer, PWR Neutronics, providing technical support for marketing efforts
+
and proposals, including custom designs and economic analyses, and supporting research and development efforts for PWR fuel designs from a neutronics standpoint. (1979-1981)
Unit Manager, PWR Neutronics, responsible for supervising a group of engineers performing nuclear fuel design and fuel management for PWR nuclear power plants, including technical support for proposals. (1982-1983)
July 25,1990 11 10 ANF 3830.051 (&B9)
l ADMehlCED hlUCLEAR FLELS CORPORATION
,n p.g SPECIAL NUCLEAR MATERIAL LICENSE NO. SNM 1227, NRC DOCKET NO. 701257 1
PART ll SAFETY DEMONSTRATION N:V-26 i
Manager, In< ore Monitoring Software Applications, responsible for managing a i
technical group performing design and installation of a software system to monitor
]
in core operation at BWR nuclear power plants. Technical support included development, testing, documentation, customer interfacing, and marketing support. (19831985)
-i 1
Senior Staff Planner, Planning and Uranium Operations, responsible for coordination of corporate wide planning efforts, including preparation of executive presentation material for Board review meetings and conducting various business 1
analysis studies. Supervised a planning analyst who maintained a commercial data base. (19851990)
)
Commercial Coordinator, Universal Testing Laboratories, Inc., responsible for supporting integration of newly acquired subsidiary into parent company.
Responsibilities included preparation of a business plan for subsidiary. (1990) i Manager, Plant Operations, responsible for management of fuel manufacturing and material recovery operations, including preparation of operating procedures, J
development and maintenance of essential material controls and inventories, and the review, initiation, and implementation of plant safety procedures. (1990-present)
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1 PART ll. SAFETY DEMONSTRATION REv.
26 11.3.7 Manager. Quality Control. D. J. Hill Education BS Chemistry and Physics 1971 Whitworth College Exariaa==
a 1971 -1973 Employed by Telodyne isotopes Company, Inc., as Assistant Scientist and Laboratory Supervisor in a low background radiolsotope counting laboratory. Activities included development of special low background counting systems and gas purification and analysis systems.
I 1973 1976 l
Employed by Hanford Environmental Health Foundation in Richland, Washington as I
~ Industrial Hygienist.
-Activities included nuclear facility safety / industrial hygiene inspections, environtnental monitoring, and methods development.
1976 - 1984 ~
Employed-by Exxon Nuclear Company, Inc., as a Chemist in the UO, Analytical Laboratory, anc' later as Supervisor of the UO, Laboratory. Responsibilities included Ouality Control analyses of nuclear fuel components, methods development, and testing and analyses in support of engineering studies, 1984 1987
]
Employed by Exxon Nuclear Idaho Company, Idaho Falls, Idaho, as Manager of Quality Control. This position involved development and management of inspection, quality i
engineering, and analytical support for a classified government manufacturing activity.
- j 987 1990 Employed by RockwellINEL as Director, Quality Operations. This position included Quality Assurance, quality engineering, and Quality Control management for the SMC project in Idaho Falls, Idaho.
i July 25,1990 11 12 ANF 3830.051 (6/89) -
AD98MCEDNUCLEARMJELS CORPORATION m p.y SPECIAL NUCLEAR MATERIAL LICENSE No. SNM 1227, NRC DOCKET NO. 701257 PART 11 SAFEW DEMONSTRATION REV.
26 1990 Present Employed by Advanced Nuclear Fuels Corporation as Manager, Quality Control. This position directs the activities of inspection, analytical and quality engineering functions in support of the ANF nuclear fuel fabrication activities.
4 autwowtut immes eart July 25,1990 11 13 ANF.3830.051 (G/89) q-
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PART ll - SAFETY DEMONSTRATION Lih 26
~ 103.8 Manager. Matellais and Schedaling.1. J. Samaritano
.u Education BChE
- Chemical Engin.,ering 1960 Polytechnic Institute of New York-MSChE Chemical Engineering 1962 Rensselaer Polytechnic Institute
!ndustrial Administration 1970-1973 Union College 1
Schenedady,NY Licenses / Memberships
- Licensed Professional Engineer, New York ~
. Licensed Professional Engineer, Nuclear Branch, California Member, American Institute of Chemical Engineers Experience 1960-1970 Employed by General Electric Company at the Knolls Atomic Power Laboratory.
l Design Engineer responsible for reactor performance analysis, reactor accideic analysis, reactor primary shield design, and in-reactor corrosion and crud buildup on nuclear fuel elements. Responsibilities included computer analysis, design, implementation, analysis of test loop experiments, and experiments in operating nuclear reactors.
Supervising' Engineer responsible for the hydraulic design of the reactor for a
- ^
nuclear powered aircraft carrier.
1970-1973 Employed by General Electric Steam Turbine Department as a Unit Manager of Shop Operations with responsibilities for a manufacturing unit of 250 machinists engaged in the precision machining of. major components for large steam turbine generators. Both
-nuclear and fossil design steam turbines were fabricated. Responsibilities also included management of -daily operations, training of personnel, scheduling utilization of equipment, production control planning, and material utilization.
AMENDMENT APPUCATION DATE.
PAGE NO:
ANF-3830.051 (6/89) l
nr;
,i ADMSNCED NUCLEAR MJELS CORPORATION.
gn p.2 ;
- SPECIAL NUCLEAR MATERIAL LICENSE NO. SNM 1227, NRC DOCKET NO. 701257:
ldi PART ll SAFETY DEMONSTRATICt; REv.
4 26
,g 1973-1974 4
Employed by General Electric Research Laboratory of the. General Electric Corporate Research and Development Center as a Chemical Engineer. responsible for the-development of a process for the separation of uranium Isotopes using high performance centrifuges, 1974-1980 Employed by Exxon Nuclear Corporation in Malta, New York, i
Senior Manufacturing Engineer responsible for developing equipment, plant a
layouts, and facility design and staffing plan for the manufacture of high performance centrifuges to be used for Isotope separation, supervised the architect _ engineer, and produced a complete plant design including associated
. cost estimates.
Assigned ir. creased responsibilities as a Project Manager for marketing, contract.
administration, manufacture, and testing of high performance centrifuges and' components utilized !n the U.S. Department of Energy Centrifuge Demonstration l.
Program. (1976) 1980-Present EmplSyed by Advanced Nuclear Fuels Corporation (Exxon Nuclear Company, Inc., prior to January 1,1987).
Manager, Production and Inventory Control responsible for plant scheduling and control of all material inventory utilized for producing. fuel, determining required quantitles and assuring material availability.
Responsible for formulating l
- requirements for an advanced computer system to !Wly control both material supply and actual production. Also responsible for empicyee training utilizing the i
new system. This sophisticated computer system was successfully implemented.
(1980)'
- ~
Manager, Materials and Scheduling responsible for planning, procuring, and managing all material requirements. in adultion, full responsibility for all plant scheduling, production control activities, including workstation scheduling, receiving, warehousing, and hternational shipping and traffic. (1983 Present) 1 L
1 July 25,1990 11-15 i
ANF-3830,051 (6/89) e 1,
,j a
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L ADMMCSDNUCLEARMRE.8 CORPORATION.
gup 7 SPECIAL NUCLEAR MATERIAL LICENSE NO. SNM.1227, NRC DOCKET NO. 701257 j
PART ll SAFETY DEMONSTRATION
- REV, 26 11.3.9: Mananer. Operations Plannina and Scheduling D. C. Lehfeldt
.j Education
-j l
3~.
BS Industrial Engineering 1954 Montana State University 1
BS_
Mechanical Engineering -
1954 Montana State University 1
- m. -
Experience 1
-1 1954-1965 j
1 l Employed by General Electric Company, Richland, Washington.
o Manufacturing' engineering on fuel fabrication for production. reactor and-N-Reactor. - (19541962) '
d Supervisor,. Equipment Development and Maintenance Engineering, N-Reactor Fuels. Involved with plant equipment and maintenance programs. (1962-1965)
--1965-1972' 1
Employed by Battelle Northwest Laboratory, Richland, Washington.
Senior Engineer on isotope source fabrication, recycle fuel equipment, Pu Al plate ln::
. type fuel development, and fueled shim rods. (19651966) m 6
' +
Manager, Radiometallurgy, involved with personnel, equipment and facilities in the l
'l examination of irradiated fuela and materials. (1967-1969) 4 Manager, Nuclear Fuels, involved with development and fabrication of UO,, MOX,
+-
y and graphite fuels. -(19691972)
R 1972-Present -
j
- i. ".
[ Employed by Advanced Nuclear Fuels Corporation (Exxon Nuclear Company, Inc., prior to' January 1,1987),
>as j
Senior and Staff Engineer involved with materials and hardware specifications and procurement for power reactor fuels, project coordination, and contract 1
administration. (1972-1984) ll7
(,p 1.
AMENOMENT APPtlCATION DATE: -
PAGE NO.:
g 1
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. Manager, Operations Planning and Scheduling, involved.with planning and scheduling fuel fabricatien activities, and logistics for national and international shipments of fuel hardware materials and waste shipments. (1985-Present) e P
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26 __
11.3.10 ' Managar latets.ttpurttv. and Licensinn - W. E. Stavig Educauon BS
' Chemistry 1956 University of Puget Sound 1
+,
m 195fE19IQ.
Employed by General Electric in the. manufacturing of nuclear fuels.
Process Development Engineer engaged in UF, conversions process and
, development, Manager, Quality Control, responsible for quality function nuclear fuel a-manufacturing, t
Manager, Operations Enginraring, responsible for prevention and~ solutions of process problems for manufacturing of nuclear fuel.
1970 Prqagnt L Employed by Advanced Nuclear Fuels Corporation (Exxon Nuclear Company, Inc., prior e
to January 1,1987).
Manager, Plant Operations, responsible for management of fuel fabrication. (1970-p 1975)
T N
Manager, Manufacturing Engineer.ing, responsible for providing technical
' directions for plant modifications and improvements. (19761980)
Manager, Plant Equipment and Design, Advanced Projects, responsible for
+
of planning engineering analyses and scope, conceptual,, and detail design for-process equipment.
Coordinate overall plant equipment arrangements for i
' increase throughput and efficiency. (1980-1983) 1 Staff Engineer, Plant Operations, responsible for engineering project interface with plant operations, define, analyze and develop implementing plans for compliance to criticality, health physics and applicable licensing documents. Audit plant operations for compliance to alllicensing activities. Member of Design Review
- group which reviewed the design and work scope for Engineering Change Notices for conformance to plant safety criteria. (19831989)
July 25,1990 11-18
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(1989-Present)
. Manager, Safety, Security, and Ucensing.
1
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t AMENDMENT APPUCATION DATE.
PAGE NO.:
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26 x
i 11.3.11 Supervisor. Safety T. C. Probasco w
Education q
BSl Microbiology 1970 Oregon State University 4'
.BS Military Science 1970 Oregon State University -
Certified Safety Professional 1982 Board of Certified Safety Professionals.
1 Experience
'1970 1972.
t Highway Engineering Technician for the Oregon State Highway Department, 1972 1975 Employed by a food processing company. Supervised chemical and bacteriological 9
laboratories in the Quality Assurance Department. (19721973)
Safety Engineer. (19731975)-
1975-Present Ir Empbyed by Advanced Nuclear Fuels Corporation (Exxon Nuclear Company, Inc., prior
. to January 1,1987).-
L Plant Safety Engineer. (1975)
Plant Criticality Safety Engineer. (1975-1984)
Supervisor, Radiological and Industrial Safety, responsible for supervising Health L
Physics Technicians, Radiological Safety Specialist, and Industrial-Hygiene i.
Specialist. (1985-1989)
K
- Supervisor, Safety, responsible for supervising Criticality Safety Specialist, Health Physics Specialist, Radiological Safety Specialist, Health Physics Technicians, and the Health Records Clerk. (1990-Present) l l-w enoutwr4epucaroucare:
July 25,1990 11-20 r
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PART ll SAFETY DEMONSTRATION -
REv.
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l 26 11.3.12 Criticality Safety Specialist L D. Gerrald Education BS Chemical Engineering 1967 University of South Carolina MS Chemical Engineering 1971 University of South Carolina J
Experience L
1968-1971 i
Employed by Westinghouse Electric Corporation at the Nuclear Fuel Fabrication Plant in L
' Columbia, South ' Carolina, as a Process Engineer responsible for the startup and L
operation of the UF UO, conversion process lines.
1971-Present Employed by Advanced Nuclear Fuels Corporat!on (Exxon Nuclear Company, Inc., prior to January 1,1987).
Process Engineer responsible for pellet fabrication process.~ (1971-1974)
]
Process Development Engineer-responsible for numerous. studies related.to several fuel fabrication processes. Developed computer codes for calculating pore size distributions for pellets using scanning electron microscope and Image -
analyzer. (1974-1981)
Process Engineer responsible for the ceramic part of the Sphere Pac project.'
p Developed equipment and parameters for drying and sintering the UO, spheres -
to be used. Also developed continuous-flow vertical sintering furnace for this -
process. (1981-1983) g Criticality Safety Analyst primary responsibility for converting several SCALE l
< modules (KENO, XSDRN,' BONAMi, NITAWL) to computer systems; responsible for verification of codes and cross sections, and numerous major criticality safety analyses were performed for operations at ANF Richland, ANFGmbH-Ungen, and X
for fuel storage racks for power reactors. Analyses have also been performed for
- submittal to the USNRC Transportation Certification Branch. (1983-Present) a AMENDMENT APPUCATION DATE:
PAGE NO -
ANF 3830.051 (6/89) u
' ADM6NCEDNRACLEARRJELSCORPORATIOff a p.g.
. SPECIAL NUCLEAR MATERIAL LICENSE NO.LSNM 1227, NRC DOCKET NO2 701257-REV,-
PART 11 - SAFETY DEMONSTRATION 26
.11.3.13 Health Physics Specialist - J. E. Pieper Education BS Nuclear Engineering Technology 1973 Oregon State University
._ Conditional Operator Certificate.
1972 BWR Power Plant Training.
Center Experience 1973-1976 Employed by'Aerojet Nuclear Company, Idaho Falls, Idaho.
LDesign engineering, (1973)
Nuclear technology.: (1983).
Nuclear -(criticality safety program, analyses, and training) and environmental safety. - (1973-1974);
Management Oversight and Risk Tree. (1974) 1976-1980 Employed by Rockwell Hanford Operations, Richland, Washington.
Nuclear Safety. (19761977)
Criticality safety _ program appraisal.
_ Review of criticality safety analyses and procedure, and system designs.
Radiological safety inspections and audits.
Health, Safety,and Environment function representative to the Chemical Processing, Waste Encapsulation, and Fractionalization Programs, (1978)
Health, Safety and Environment Design Review Coordinator. (1978-1980)
Safety review and approval of new projects and designs.
July 25,1990 11-22 ANF 3830.051 (6/89)
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- SPECIAL NUCLEAR MATERIAL LICENSE NO. SNM 1227, NRC DOCKET NO. 701257.'
"i PART ll - SAFETY DEMONSTRATION REV.
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26 Tecnnical consultant on DOE requirements for packaging and shipping j
radioactive materials.
1.
Flying Tigers Hazardous Materials-Shipping Seminar.' arid Workshop.
(1979)
Radiological Engineer in the Decontamination and Decommissioning Program.
1 (1980) ~
l 1981-Present l
Employed by Advanced Nuclear Fuels Corporation (Exxon Nuclear Company, Inc., prior to January 1,1987).
l L'
Ucensing Engineer responsible for assuring compliance ~ with the health physics
- =
requirements of the license for a uranium fuel fabrication facility, and performing
,j l
criticality analyses in support of the facilities operation.
L Internal Radiation Dosimetry. (1983)
Introduction to Power Reactor Health Physics. (1983)-
Health Physic Certification Preparation. (1983,1985-86)
Blokinetics and Analysis of Uranium in Man. (1984)
Radioactive Materials Training Course (DOT).' (1984)
Internal Dose Assessment. (1985) i AMENOMENT APPUCATION DATE.
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^
ii3.14' Radiological Safety Specialist - E. L Foster l
Education t
High School Diploma 1960 Richland, Washington -
Columble Basin College;,
' Nuclear Weapons Technician School U.S. Air Force
= -
a Techr'lcal courses completed:<
l l
N Radiation Technician Chemistry Course
' Radiation Dosimetry; j
-Biological Effects of Radiation:
l
' Radioactive Waste. Disposal
+-
- Environmental Monitoringi i
Elementary Nuclear Physics 1
- Mathematics'in Radiation Protection i
%1
= lonizing Radiation Measurements l
' Radiation Protection Techniques f
Ee W
- Air Sampling Principles and Evaluations 1
Radioactive Decontaminatio.n Principles Radiation Exposure Records.
Disaster Monitoring.
Experience
= 1967-1971; Employed by Battelle Northwest in Richland, Washington as a Radiation Monitor in the
- development and application of health physics programs'for radioactive chemical
' separations' plants, multi-curie laboratory operations, and nuclear fuel manufacturing.
, f Performed monitoring duties during major cleanup and modification of plutonium hot cells and gloveboxes.
Direct participation in survelliance of effluent from: plutonium facilities while assigned to an environmental monitoring group.
Direct participation in setting up routine health physics program for PRTR.
Completed special assignment involving modification of plant air monitoring program.
AMENOMENT APPUCATION DATE: -
PAGE NO.:
ANF.3830.051 (6/89) ce
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i 26 1971-Prosent Employed by Advanced Nuclear Fuels Corporat.On (Exxon Nuclear Company, Inc., prior
- to January 1,1987).
Health Physics Technician involved primarily in all phases of the radiological safety program throughout the entire plant site. (19711976)-
' Technician Specialist, Radiological Safety. (1977)
Radiological Safety Assistant. (1980)
I Radiation Safety Officer for Washington State Ucense. (1984)
Radiological Safety Specialist responsible for implementation of radiological safety 1
training program, dosimetry program, bioassay program, writing of Radiation Work Procedures, reporting of radiological conditions to plant supervision. (1985) t Completed training course in Respiratory Protection at Nuclear Power Plants.-
(1985):
i Completed training course as a Padiat'an Safety Officer. (1986)
Completed training course in Air Sampling. (1986)
Completed training course in NVLAP Accreditation. (1987)
Completed tral.ung course r. Hot Particle Dosimetry. (1987).
Coinpleted training course in Radiation Detection and Measurement. (1989) s AMENDMENT APPUCATION DATE:
PAGE NO.:
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26 L 11.3.15 Health Physics Technician E. S. Arel
.,[
' Education
- s, d]
- Diploma.
1088 Crookston, MN
^
< Medical Training 1969-Ft. Sam, Houston, TX k
i 1 Radiation Theory ll:
1990 Columbia Basin College l(Radiation Protection Technology)
Pasco, WA HPT Training -
1990 Advanced Nuclear Fuels 1
Experience m;
.a
( 1976-Present :
LEmployed by Advanced Nuclear Fuels Corporation (Exxon Nuclear Company, Inc., prior to; January.1,1987).
6' l Technician in the UO, Fdel Fabrication Operation. (19761978).
LTechnician in the UO, Fuel Fabrication Operation. (1982-1984).
a.
+ '
' Traffic Controller in Purchasing & Logistics. -(1984-1990)
Health Physics Technician'in Safety, Security, & Ucensing. (1990-Present) a is,b
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AMENDMENT APPUCAftON DATE:
PAGE NO:
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gup.2 SPECIAL NUCLEAR MATERIAL LICENSE NO. SNM.1227, NRC DOCKET NO. 701257 :
PART 11 SAFETY DEMONSTRATION REY.
26 11.3.16' lisalth Physica Technician D. L Belt Education Diploma 1954 Columbia High School 1975 Columbia Basin College Radiation Protection Training 1 1977 Battelle Northwest National Registry of Radiation-1979-1982 Protection Technologists
- Technical courses completed:
- Engineering Laboratory Techniques
, Radiation Control Practices:
4 Theory of Power Plant. Operation Radiography Techniques
. Dosimetry
' Radiation Shielding and Radioactive Material Containment First Aid Training -
2 Annual First Ald Refresher Courses (1977-1986) -
. Annual Plant Emergency Cadre Training (1977-1986) _
y Experience 1975-Present Employed by Advanced Nuclear Fuels Corporation (Exxon Nuclear Company, Inc., prior
- to January;1,1987).
Technician in the UO fuel fabrication operation. (1975-1977) 2
-- Health Physics Technician t esponsible for overall auditing, inspection, monitoring, and evaluating health physics-related criteria. The application of procedures used
-in the control of radiation, radioactive materials, and criticality are also functions of this position. Responsible for auditing, recognizing and evaluating radiological and nuclear hazards, and/or taking emergency action as necessary to protset-hoalth and property. Additional responsibilities of this jet include training of new
. employees, maintaining records of bioassay, person 1el monitoring and survey results, exposures, room air and exhaust sampling and monitoring. Daily audits are performed of compilance to State and NRC lice nse conditions. Daily air AMENDMENT APPtlCATION DATE:
PAGE NOJ ANF-3830.051 (6/89)
f
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PART 11 - SAFETY DEMONSTRATio.]
REV; 26 sampling, and analysis of same of'all-areas of the plant. Responsible for -
environmental monitonng, H,0 sampling of waste lagoons obtaining environmental (fluoride and vegetation) samples within a 10-mile radius of plant. Also included as major responsibilities of this position are recordkeeping, issuing reports and h"
l
. entering data in computerized Environmental Monitoring Program. (1977 Present) :
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26 11.3.17 Health Physics Technician L G. Bradley Education Diploma 1947 Salem, Oiegon UFAFI Program 1962-1965 U.S. Air Force j
Commercial Pilot Rating 1968 Pasco, WA j
Radiological P(otection Technical 1983 Rockwell Hanford Company Certification Richland, WA Health Physics Technician Certification 1987 Experience 1962 1965 U.S. Air Force, Disaster Control Ofncer, responsible for training Disaster Control Teams throughout the squadron, for setting up decontamination facilities, and training personnel in the use of radiation detection devices.
1 1965-1974 l
i Worked in various construction projects as a heavy equipment operator and truck driver; j
was also employed as an agriculture pilot for H&W spraying, Midland, Texas.
1974-1984 Employed by Atlantic Richfield as a Radiation Monitor.
1984 Present Employed by Advanced Nuclear Fuels Corporation (Exxon Nuclear Company, Inc., prior to January 1,1987) as a Health Physics Technician.
l l
Dismantle plutonium hoods in the Specialty Fuels Building. (1984-1987) l i
" " ' " " ' " ' ^ ~ ^ " " ^ ' '
July 25,1990 11-29 ANF 3830.051 (6/89)
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PART liiSAFETY DEMONSTRATION REv.
26 11.3.18 Health Physics Technician - J. D. Cudmore a
Education l Diploma [
1946.
Washburn, VVI '
.x 3
h(
industrial Welding / Burning -
Ashland Vocational School-7m Ashland, Wi-f ~,.
(h "i d
. General -
Columbia Basin College yy U.S. Army. Airplane School Nara, Japan Business Courses -
-Northland College Ashland, WI >
Technical courses completed: -
. Elementary Nuclear. Physics
- lonizing Radiation Measurements
^*-
' Air Sampling Principles and Evaluations i
Shipments of Radioactive' Materials Radiological. Civil Defense M_athematics In Radiation Protection -
4
- Radiation Protection Techniques.
Radioactive Decontamination Principien j
Radiation Exposure Records :
9 Disaster Monitoring Experience
)
(1953-1971-Worked in Richland, Washington in the following capacities related to radiation protection:
' Chemical Technician: assisting Chemists and Engineers in operation of. the-radioactive hot cellliquid waste solidification techniques. Knowledge of chemistry, i
chemical tank makeup, vacuum and pressure, control rod Instruments, and L'
manipulation of the same. Also filled, shipped, and received rad.ioactive samples and liquid casks. Complete knowlecige of decontamination of equipment (large and small), including personnel.
AMENDMENT APPLICATION DATE.
PAGE NO.:
ANF.3830.051 (6/89)
.m
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AD%6NC8D NUCLEhit 9lUIELS CORPORATION m p.7 SPECIAL NUCLEAR MATERIAi. l.lCENSE NO.- SNM 1227, NRC DOCKET NO.1701257 PART ll SAFETY DEMONSTRATION REV.
26
- \\
Manipulator-Operator experience in Am, Pu, Pm, Cs, Co, Np, Sm separation, and -
M purification using lon exchange columns and glovebox techniques, i
Made radiation surveys of radiation zones and non radiation zones, report, and; recommend; corrections for unsatisfactory conditions.
Made surveys 'and Li authorized release of equipment. Prescribe dose rates and clothing requirements for entry into' radiation zones and for work within these zones in contaminated-equipment and radioactive material. Investigate the circumstances leading to Ll clothing or skin contamination or uncontrolled contamination spread.. Prescribe the necessary respiratory protection after taking air samples and evaluation.
- Provide either constant or intermittent monitoring of radiation zone work. Made legible, concise, accurate, and complete records of all activities. Provide radiation-protection training to operating and maintenance personnel.
-1 1971-Present
-j Employed by Advanced Ntelear Fuels Corporation (Exxon Nuclear Company, Inc., prior to January 1,1987) as a Health Physics Technician.
i 1
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July 25,1990 11 31 l
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REv.
26 11.3.19 Health Physics Technician D. A. Marlin Education Diploma 1950' Selah, WA Chemical, Biological and Radiological 1952 Gifu, Japan School ~ ~
Radiation Monitoring Training Programs-1954 1970 Richland, WA Radiation Technology 1964 1966
. Columbia Basin College 1
' Electrical Appliance Repair 1969 Richland, WA Experience 1954-1973 Employed in' Richland, Washington in the following capacities related to radiation monitoring:
Provided radiation protection for personnel !n the Hanford laboratory divisions consisting of constant scientific experiments, storing contaminated liquid waste, and disposing of extremely high radiated and contaminated solid waste Provided
, routine and special surveys to promote contamination and exposure control.
Radiation Monitoring Journeyman providing radiation monitoring for all crafts needed to maintain and operate both the graphite reactors and a dual-purpose power reactor.
Radiation Monitoring Supervisor supervising the activities of Radiation Monitoring Journeymen during reactor operations and shutdown. Scheduled and assigned this manpower to various jobs with consideration to the requirements of job safety, labor costs, radiation exposure control, and coordination with operating and -
maintenance groups, Provided radiation protection for personnel in all phases of operations and
-+-
maintenance in nuclear reactors Provided routine and special survey to promote contamination and exposure control. Advise on requirements, procedures, and optimum methods for accomplishing work, including shielding, decontamination and remote operations. Collected and analyzed data for use in determining present and future needs in radiation protection.
Auenoutui amcaron can; July 25,1990 11-32 ANF-3830.051 (6/89) 1
+
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26 Provided radw., protection for th,,h *La personnel.. Burying radioactive liquid; I
waste and processing waste to remove different elements in each process until" waste was made into a hard state.
+1 In conjunction with tank farm work, covered laboratory work dealing with sampling ;
radioisotopes in gloveboxes and hoods. Provided control of radiation exposure i
. by monitoring and using preventive shielding methods, and keeping areas clean by constant smearing and monitoring with survey Instruments.
1973-Present -
i Employed by Advanced Nuclear Fuels Corporation (Exxon Nuclear Company, Inc., prior to January 1, t987) as a Health Physics Technician.
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PAGE NO:
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11.3.20 Health Physics Technician - P. A. McBride 3
Educati.QD Diploma' 1969
. Idaho Falls, ID i
1 Technical classes completed:
1981 Eastern Idaho Vocational -
Technical School J':
Radiation. Protection Idaho Falls, ID
- Instrumentation :
l!
' Technical Mathematics a
' Industrial Relations 3
- Decontamination Techniques Industrlal Safety.& Hygiene l Biological Effects of Radiatic.i
. Exoerlencel s
1981-1962 i
. Employed by Interstate Nuclear. Services in Pleasanton,-CA ~ as a Health Physics Technician in Development and Application of the Radiological Safety Program.
1982 1986 J
' Employed by. Rockwell international Corp. at the Hanford Nuclear Area as a Senior i
.RadiationLProtection Technician involved in maintenance and application of the L
' Radiological Protection Program.
p:'
p 1987-1990 1
' Employed as a Contract Senior _ Health Physics Technician at H.B. Robinson, Trojan, E
Vermont. Yankee, Palo Verde, Diablo Canyon,i 1 Onofre, and.WPPSS during all phases of their refueling operations.
1 11990 Present
' Employed by Advanced Nuclear ::uels. Corporation as a Health Physics Technician
. involved in all phases of the Radiological Safety Program.-
L L
AMENDMENT APPUCATION DATE.
PAGE NO:
AN F-3830.051 (6'89)
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ADGUdCED NUCLEAR M,ELS CORPORATION '
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q 11.3.21 Health Physics Technician 4. D. Nelson Education Diploma 1963-Spokane, WA Mechanical Drafting Course 1966 Highline Community College-il Seattle, WA Highway Department Engineering 1966 Washington State ' niversity i
U Technician Course Pullman;WA General Education & Business 1970-Columbia Basin College 1974 Pasco, WA Health Physics TechnicianJ 1974-Westinghouse Hanford b
' & Certification
-1988
- Preparatory Class for NRRPT Exarn
-1976 Columbia Chapter,.HPS Intro to Health Physics 1976
- WSU Joint Center -
1 l
Richland, WA y
iMember:. NRRPT Experience j
1 1
w
+
1969-1974
~
Employed by U.S. Testing Co.,'Inc., in Richland Washington as a Dosimetry Technician,
' Dosimetry Supervisor. '
r i1974 1988 j
l.,
' Employed by Westinghouse Hcnford in Richland, Washington. Worked as a Senior L
- Health' Physics Technician at fuel fabrication facilities, radiochemistry labs, hot cell-4 facilities,.. waste management facilities, sodium-cooled test reactor (FFTF), and 3
decommissioning'of shutdown defense reactor facilities.
1 v:
)4 1962 Employed by Nuclear Support Services as a Senior Health Physics Technician at the River Bend Nuclear Plant in St. Francisville, Louisiana.
auenoueur neucaron oare:
July 25,1990 11-35 k
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.- J S.
' Employed by Bartlett Nuclear Service as a Senior Health Physics Technician at the Trojan Til A
L Nuclear Plant in Rainier, Oregon -
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1990-Present l
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' Employed by Advanced Nuclear Fuels as a Senior Health Physics Technician,
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26 11.3.22 ' Health Physics Technician - J. A. Rosscup -
Education
- Diploma 1954 Glasgow, MT
)
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' Columbia Basin College.
1975 1976 Health Physics Technician Training
~1978 t
Advanced First Aid Training Course 1979 q
i Experience j
J 1976 Present j
- Employed by Advanced Nuclear Fuels Corporation (Exxon Nuclear Company, Inc., prior 2
. to January 1,1987).
' Technician in the UO fuel fabrication operation. (1976-1977) 2 Health Physics Technicianc (1978-Present) -
e J
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.i auenousui apeticatioN DATE:
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- $1.3.23' Health Physics Technician - W. W. Smith L_
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Education 1
0 Diploma' 1956
[.e
? Radiation Technology 1984 Goinick Home CmTe4.pm,dence j
p i
t,M NRRPT Certification Course' 1985-University of Washington Richland, WA,
j M '..
o Advanced and Basic First Aid (currentlyLcertified)
(n v.
- 7 #.
Experience s
1980-Present
]
. Employed by Advanced Nuclear Fuels Corporation (Exxon Nuclear Company, Inc., prior
- to January 1,1987) as a Health Physics Technician.
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PART 11 - SAFETY DEMONSTRATION 26
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"11.3.24 Health Physics Technician G. A. York -
Education 1
Diploma 1970 Walla Walla, WA-(Western Washington State College.
1970-1971 Bellingham, WA.
y
,3 Walla Walla Community College 1977 1978-Walla Walla, WA '
4 Hanford Radiation Mon 4 tor Training 1979 L Program
.A Columbia Basin College 1981 1983
. NRRPT Cer+1tication Course 1985.
University of Washington -
Richland, WA.
Experience
=
.1979-Present -
I
- Employed by Advanced Nuclear Fuels Corporation (Exxon Nuclear Company, Inc., prior l to^ January _1,1987) as c Health Physics Technician.
1
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PAGE NO :
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- SPECIAL NUCLEAR MATERIAL LICENSE NO. SNM 1227, NRC DOCKET NO. 7012571 PART 114 SAFETY DEMONSTRATION REV.
26!
11.3.25 Manager. Regulatory Compliance' C. W. Malody, Jr.
Education AB Chemistry 1950 University of Kansas Experience 1950-1963 j
Employed by General Electric Company, Richland, Washington.
Process Control Engineer responsible for operating procedures, flow sheet testing,-
devising process control programs for control of product purity and nuclear safety, g
and plant technical support.
s Manager, Uranium Oxide, responsible for operation, maintenance, and radiation:
~*
~ monitoring.
1963-1964 c
_ Employed by Isochem, Inc., Richland,- Washington.
l Manager, Uranium Oxide.
- - Manager, Purex Operations, responsible for plant operations, process control, and
' radiation monitoring.
M.1gIZ Employed by Atlantic Richfield Hanford Company, Richland, Washington.
Manager, Process Co_ntrol Engineering, responsible for process control, nuclear i
safety control, process test authorization, and direct technica! support to the Purex.
' Piant. (t964-1968)
. Manager, L Technical Services, responsible for $5 million annual budget,
.approximately 230 employees in three process control laboratories, and radiation
' and monitoring control. (1968-1970)
Manager, Purex Plant, responsible for annual budgets greater than $10 mil. lion,
- i and managed approximately 160 employees in operations, maintenance, process engineering and radiation monitoring. (1970-1973) nuesou ~14,pucaron oars.
. July 25,1990 11-40 ANF.3830.051 (6/89)
(.
AD%Sn0C8D hlUCLRAR FUELS CORPORATION gn p.2 SPECIAL NUCLEAR MATERIAL LICENSE NO. SNM 1227, NRC DOCKET NO. 701257 I
PART ll SAFETV DEMONSTRATION lREV.
[26 I
Manager, Production Department, responsible for annual budgets greater than $25 1
million and managed more than 700 employees in three major processing i
operations, maintenance, process engineering and radiation monitoring.
(1973-1976)
Manager, Production and Waste Management, responsible directly to the President for the overall direction of 1200 employees and more than $40 million annual operating budget. Member of Company's negotiating team during Union j
l C r.tiact renewals. Also member of an Executive Council determining Company priorities and resource allocations. (1976-1977) j 1977-Present l F.nployed by Advanced Nuclear Fuels Corporation (Exxon Nuclear Company, Inc to January 1,1987).
Consultant responsible for providing consulting services in support of the proposed reprocessing and spent fuel storage programs. (19771979)
Manager, Process Engineering, responsible for keeping abreast of research and i
development activities in the field of reprocessing. This was accomplished by l
maintaining contact with and providing supporting studies for those DOE sites involved in the back end of the fuel cycle such as ORNL, Sandia, Idaho Falls, etc.
(1979-1981) l c
Manager, Ucensing and Compliance, responsible for all licensing activities and
{
criticality and radiciogical safety programs for the fuels fabrication plant and research laboratory. (1981-1985)
I Manager, Corporate Ucensing, responsible for overall licensing and regulatory responsibility for fuel production and transportation acHvities, and for defining, administering and auditing health physics, environmental surveillance, ALARA, nuclear criticality safety, and nuclear material safeguards programs. (1985-1989) i i
Manager, Regulatory Compliance, responsible for overalllicensing and regulatory l
responsibility for nuclear activities, and for establishing health physics, nuclear l
safety, hazardous materials safety, environmental safety, ALARA, and nuclear material safeguards programs in compliance with legal and regulatory requirements, and sound industrial practices. (1989-Present) 1 l
^ " ' " " ' " ' ' " * " " ^ ' '
July 25,1990 11-41 ANF-3830.051 (6/89)
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,s ADHSNCEDNtJCLEAh.*nLS CORPORATOV j
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.,qq,y SPECIAL NUCLEAR MATERIAL UCI JSE No. $NM 1227, NRC DOCKET NO. 70.M57
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PART ll. SAFETY DEMONSTRATION AEV-26 j
1 11.3.28 Staff Specialist 4afeguards J. B. Edgar j
Education g
l:
l BS Physics 1965 Whitworth College
]
MBA Buslaess Administiction Finance 1970 University of Washington i
Experience
.1965196Z Employed by Douglas United Nuclear, Richlana, Wash 1gton.
)
l L
Process Physicist Performed physics calculations and advised, from a reactor I
physics standpoint, on the operation of a Hanford production reactor.
)
190Zdf.Q Employed by Battelle Northwest Laboratories, Richland, Washington.
l Reactor Engineer Supervised two technicians in the operation, maintenance, and -
L data collection for experiments in Piutonium Recycle Critical Facility Also assisted I
in analysis of data. (196719661)
-j Nucidar Safety Specialbf. Provided guidance for Battelle Northwest operating components and performed Audits, reviews, and wrote moquals and safety
)
analyses in the araa of nw: lear safety. Interfaced with AEC on nuclear safety l
questions (1969-1970;
~
i l
1970-1973 Employed by Westinghouse Hanford, Richland, Washhigton.
Supervisor, Materials Management Supervised three engineers, one technician, s
and two clerks in a nuclear materials accountability function for Westinghouse Hanford. Provided expertise in packaging and shipping of radioactive materials.
1 Criticality safety specialist for three laboratories, including preparation of safety j
analys!s reports and criticality afety specifications and auditing for compliance i
with applicable limits.
i auewovewt amication oats:
July 25,1990 11 42 ANF 3830.051 (W89)
ADHSNCEDNUCLMARRELSCORPG3ATION gu p.2 SPECIAL NUCLEAR MATERIAL elCENSE NO. SNM 1227, NRC DOCKET NO. 701267 J
l PART ll. SAFETY DEMONSTRATION REV.
l 26 192,3 Present l
Employed by Advanced Nuclear Fuels Corporation (Exxon Nuclear Company, Inc., prior to January 1,1987).
Senior Materials Engineer Managed Exxon Nuclear's uranium and plutonium inventories throughout the world from to point at which title transferred to Exxon Nuclear. Administered criticality sa'ety program for fuel fabrication facilities at Richland. Provided special nucim material traffic oxpertise on state and federal regulations. (19731977)
Manager, Traffic Operations Managed the traffic and warehousing function for
+
Exxon Nuclear Company at its Richland site. Managed the CNpment of hardware, UO, pellets, and miscellaneous items from ENC Richland to ENGmbH-Ungen in support of ENGmbH fuel fabrication. (19771979)
Contract Administrator (Bellevue, Washington) Administered contracts for six reload fuel customers (four domestic and two foreign) for the sa;e of reload fuel, uranium, and technical services.
Responsibilities included evaluation of compliance _ with contract commitments; contract execution including commencement of work, progress reports, invoicing management, and closeout' at completion of work; and marketing interaction including proposal writing and assisting in contract negotletions. (1979-1988)
Staff Specialist Safeguards Provide technical expertise on safeguards; act as 4
Accountability Coordinator and Measurement Control Program Coordinator; act as working level contact with NRC on safeguards matters; conduct annual measurement review; prepare and maintain. ANF's Safeguards Plan (ANF 12);
provide safeguards training for plant personnel; host NRC safeguards audits and biennial Ad Hoc Committee review of safeguards activities; maintain knowledge r
of current radioactive material transport regulations; prepare and maintain Radioactive Material Shipping Standard (Chapter 5) of ANF's Safety Manual (ANF-30); review radioactive material shipment for compilance with regulations; prepare and maintain ANF's SNM Physical Protection Plan (ANF 538) (1988-Present) l awe-ouent aceucation.omie.
July 25,1990 11-43 i
ANF 3830.051 (6/89)
ADMSNCED ANJCLEAR FtEE,3 CORPORATION
,u p.y SPECIAL NUCLEAR MATERIAL LICENSE NO. SNM.1227, NRC DOCKET NO. 701257 e
PART ll SAFETY DEMONSTRATION REV.
2S 11.3.27 Environme ital Engineering Specialist. S. R. Lockhaven Education BA Biology 1974 CentralWashingtonUniversity BA
. Environmental Studies 1976 CantralWashingtonUniversity Industrial Hygiene Training Courses 1979-Present Experience i
i 1976-Present l
Employed by Advanced Nuclear Fuels Corporation (Exxon Nuclear Company, Inc., prior to January 1,1987),
Senior Analytical Laboratory Technician. (1976)
Industrial Hygienist ~ duties included scheduling environme, ital sampling, environmental data feview, and assisting the Plant Criticality Safety Engineer.
(1979) r Plant Criticality Safety Engineer. -(1986)
+
Industrial Regulations Specialist. (19891990)
Environmental Engineering Specialist. (1990 oresent)
[
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5 1
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AG NO-
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i ADt86hMDNUCLEARMElACORPORATION m y.g SPECIAL NUCLEAR MATERIAL LICENSE NO. SNM.1227, NRC DOCKET NO. 701257 PART 11 SAFETY DEMONSTRATION REV.
26 11.3.28 Vice President Engineerina Division T. A. Bjemard Education BS Physics 1971 Kalamazoo College MS Nuclear Enginooring 1976 Massachusetts Institute of Technology PhD Nuclear Engineering 1977 Massachusetts institute of l
Technology i
Experience 1971-1973 Employed by Connumers Power Company, Jackson, Michigan.
a Miscellaneous tasks in the Nuclear Operations Department related to the nuclear fuel cycle.
1974-Present Employed by Advanced Nuclear Fuels Corporation (Enon Nuclear Company, Inc., prior to January 1,1987).
l l
Nuclear Safety Engineer developing LOCA analysis models for the licensing of boiling water reactors.
Leave of absence from Enon Nuclear Company to complete Masters and PhD degrees at the Massachusetts Institute - of Technology in Cambridge, Massachusetts. (19751977)
Production and Engineering Engineer responsible for the development of l
computer models for LOCA analysis, and Project Manager for ovvelopment of advanced BWR fuel designs.
r gaeoring Representative, Engineering and Production, ENGrnbH, Lingen, e
FadFal Republic of Germany, responsible for the implementation of design and process engineering specificatione in the fuel fabrication plant.
s h
auenowestapeucaronpats-July 25,1990 11-45 ANF 3830.051 (6/89)
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- ADnunfADNUCLEAMMELSCORPORATICW mp y SPECIAL NUCLEAR MATERIAL LICENSE No. SNM 1227, NRC DOCKET NO. 701257 PART l'
- flAFETY DEMONSTRATION REv.
26' Manager, incore Monitoring, responsible for developing, maintaining, and installing l
computers and software systems for the on line core monitoring of BWR's and PWR's, i
Manager, Technology Applications, ENil, Brussels, Belgium.
Manager, European Business Operations, ENil, Brussgls, Belgium.
1 Vice President and Manager, European Business Operations, ENil, Brussels, j
Belgium, responsible for providing angineering and management support for European nuclear fuels business.
q Vice President and Manager, European Business Operations, ANFl, Brussels, l
+
Belgium, responsible for European operations in support of ANF's European fuels q
business, including business development. (1987-1989)
)
Via President, Engineering Divisk
'esponsible for the engineering aspects of nucisar fuels business including research, fuel design, neutronics and fuel
)
management, fuel licensing and safety engineering, corporate computer services, and process engineering and equipment engineering (in support of the fuel i
fabrication facilities). Member of Advance Nuclear Fuel's Executive Committee.
(1989-Present) l
?
l July 25,1990 11 46 ANF 3830.051 (&B9)
_. ~ _.,
l i
1 I
ADuSNCEDNUCLEARRELSCORPORATION i
m p.g SPECIAL NUCLEAR MATERIAL LICENSE NO. SNM.1227, NRC DOCKET No. 701257 i
PARTll SAFETY DEMONSTRATION REV.
26 11.3.29 Manager. Research and Product Development G. L Ritter t
Education j
BA
- Chemistry 1961 Pacific Lutheran University BS Chemical Engineering 1962 University of Washington MS Chemical Engineering 1964 University of California Experience 1964 1965 Employed by General Electric as a Process Engineer at the Hanford Purex Plant and i
Semi Works Facility.
1966.1968 Employed by Isochem, Inc., as a Senior Process Engineer responsible for developing the technology to recover fission products (Cs 137 Sr 90, Tc 99 and Pm 147) from Hanford high-level liquid wastes, 1968 1971 Employed by Atlantic Richfield Hanford Company.
Senior Engineer responsible for defining and planning research and development programs for managing radioactive wastes.- (19681970) l Manager, Separations Process Engineering, responsible for process control and J
process development support. (1970-1971)'
]
1971 Present
)
s Employed by Advanced Nuclear Fuels Corporation (Exxon Nuclear Company, Inc., prior to January 1,1987).
Senior Engineer responsible for portions of the technology to support a proposed commercial reprocessing plant. (19711973)
Manager, Reprocessing Process Engineering, responsible for all procen technology and safety analyses for the commercial reprocessing plant project.
(1973 1977)
July 25,1990 1
ANF 3830.051 (&89)
I j
m j
. AWA6Mll8DMotu castMELSCORPORATION l
gup.2 SPECIAL NUCLEAR MATERIAL LICENSE No. SNM.1227, NRC DOCKET NO. 701257 i
PART11 SAFETY DEMONSTRATION REV.
26 i
Manager, Reprocessing Engineering, responsible for engineering activities to support reprocessing projects performed for the Department of Energy and Oak Ridge National Laboratories. (19771979)
.l Vice President, Technical Department, responsible for all technical activities for I
supporting the Idaho Chemical Processing Plant at the Idaho National Engineering Laboratory. (19791981)
Manager, Process and Engineering Development, responsible for process engineering and research and development. (19811983)
Manager, Process and Equipment Engineering, responsible for all process and project engineering support. (19831985)
Manager, Fuel Engineering and Technical Services, responsible for nuclear fuel f
management, licensing and in core monitoring. Also responsible for Fuels Research and Development and Corporate Computer Services. (19851990)
Manager, Research and Product Development, responsible for process and l
product development activities, including development of analytical m',thodologies to perform neutronic, mechanical, and safety analysis calculations to design and license the nuclear fuel products. (1990-Present) i i
i
]
l l
l l-1 L
awesoutur amcaron cate July 25,1990 11 48 l.
l.
ANF 3830.051 (&89)
I i
1 1
ADMUMDMJCLEARMMACORPORATKW
}
gnr.2 SPECIAL NUCLEAR MATERIAL LICENSE NO. SNM 1227, NRC DOCKET NO. 701257 1
]
PART 11 SAFETY DEMONSTRATION REV-26 j
11.3.30 Mananer. Manufacturina Technoloav 1. J. Urra Education 1
1 BS Chemical Engineering 1971 University of Idaho J
MS Chemical Engineering 1972 University of Idaho i
Experience 1972-1974 1
)
Employed by All!ed Chemical Corporation, Idaho Falls, Idaho.
Engineer responsible for conceptual and feasibility studies, economic and i
consequence analysis, and project design support. Served as a technical l
~ representative at' Oak Ridge' National Laboratory on the HTGR development program.
- 1974-Present Employed by' Advanced Naclear Fuels Corporation (Exxon Nuclear Company, Inc., prior '
to January 1,1987) in Richland, Washington, Oak Ridge, Tennessee and Ungen, West Germany.
~
Engineer, Reprocessing Process Engineering,' responsible for the ENC uranium 4
conversion development program at ORNL Pilot plant ard laboratory process.
- i equipment was designed, constructed, and tested for conversion of uranyl nitrate to UO,, UO, fluorination to uranium oxide, and purification of UF. (19741977)
Engineer, Reprocessing Process Engineering, responsible for lead processing engineering for the uranium conversion portion of the ENC fuel reprocessing i
plant. Served as Task Leader in a DOE sponsored advanced fuel cycle study.
'(1977 1978)
Engineer, Design and Mechanical Development, responsible for design of uranium chemical operations and dye solution processing systems for the JNAl Experimental Test Facility, and conceptual studies of a commercial scale laser isotope separation plant. Directed design activities of an A/E firm. Prepared conceptual plant designs to define capital and operating costs. Prepared process flow sheets, selected and sized equipment, material of construction, thyouts, etc.
L (1978-1 0 1)-
L autwowtNT annication oats.
July 25,1990 11 49 ANF-3830.051 (&'89) i
1 ADuMCEDNiW.LEARMELS CORPORATION m p.2 SPECIAL NUCLEAR MATERIAL LICENSE NO. SNM 1227, NRC DOCKET NO. 701257 PART 11 SAFETY DEMONSTRATION REv.
26 Str.ff Engineer, Dry Conversion Process Development, responsible for the Dry Conversion U9velopment Program including design, construction and experimental opeation of a pilot plant, and a prototypical test facility. Developed and demonstrated a unique dry process for conversion of UF, to ceramic grade UO, (patent pending). The dry conversion process is being installed in the ANFGmbH fuel fabrication plant.
Directed and coordinated process and equipment design, equipment procurement, installation, and process development.
(1981 1905)
B Senior Staff Engineer, Process and Equipment Engineering, responsible for
+
supervision, planning, and technleal direction for the Ungen UF, Dry Conversion project ($8.5 million) through design, licensing, procurement, construction, and startup. Responsibilities included providing technical direction of related process and equipment development work. (1986-1989)
Manager, Chemical and Ceramic Development, responsible for providing ongoing and long range engineering and development support to fuel production and r
waste management operations in the chemical and ceramic development areas.
Responsibilities include development of new and improved processes and
- processing techniques which improve product quality, and reduce manufacturing costs. (19891990) l Manager,' Manufacturing Technology. (1990-Present) i l
1
)
auc=ourwt amicaron oar' July 25,1990 11 50 l
ANF-3330.051 (E'89)
l
.i m...-
)
ADMANCEDMJCLEARREl& CORPORATION guy.g SPECIAL NUCLEAR MATERIAL LICENSE NO. SNM 1227, NRC DOCKET NO. 701257 PART 11 - SAFETY DEMONSTRATION REV.
)
26 1
11.3.31 Manapr. Materiale Research - R. A. Busch Education BS Metallurgical Engineering 1961 Rensselaer Polytechnic institute i
MS, Materials Science 1963 1966 University of California PhD 1
1 i
Post Doctoral Fellowship, UC Experience 1966 1979 Employed by Battelle Northwest as a Senior R(search Scientist responsible for contract research and development programs sponsored by government and industry. Major portions of effort in coating deposition, characterization and actinide elements, j
1979-Presort Employed by Advanced Nuclear Fuels Corporation (Exxon Nuclear Company, Inc., prior to January.1,1987).
]
Manager, Materials Research, responsible for materials' aspects of fuel and 1
cladding development and characterization including laboratory work with nuclear
.)
materials.
L.:
)
L L
l AMENDMENT APPL, CATION DATE PAGE NO.:
ANF 3830.051 (G'89)
4,. 2 l
ADuMMDMJCLEARMMEACORPORATION gn p.2 SPECIAL NUCLEAR MATERIAL LICENSE No. SNM.1227, NRC DOCKET No. 701257 PART ll SAFETY DEMONSTRATION REV.
26 i
11.4 Operating Procedures i
Plant operations are conducted according to written procedures. The ' rocedures p
are written by N Manager, Plant Operations, or his designee. They are approved by the Managers of User Group; Quality Control; Safety, Security, and Ucensing; Piant Engineering; and Process Engineering. These procedures include, by reference, appropriate criticality safety specifications, radiation work permits, and other safety-related or pertinent documents or precedures. The procedures are documented and issued by Document Control to appropriate personnel and locations. There are mini-libraries located within the various operating facilities which contain copies of the approved operating procedures for ease of access by operating personnel.
j 11.5 Trainina 11.5.1 initial Trainina I
Each employee is provided initial instruction adequate to allow them to safely start on the job training by his/her manager or supervisor. This initial instruction includes emergency procedures, if the employee routinely works with special nuclear material, radiation protection and criticality safety, requirements and procedures will be included.
Within two weeks after starting work, full instruction in Standard Operating Procedures (including instrumentation and control, methods of dealing with process malfunctions, control of hazardous chemicals, control of contamination and decontamination procedures), industrial safety, fire protection, emergency response procedures, radiation protection (including Al. ARA practices, nature and source of radiation, Interactions of radiation and matter, biological effects of radiation and the use of radiation monitoring equipment and step-off pad procedures) and criticality safety, requirements and procedures will be provided. The degree of training is commensurate j
with each employee's position in the Company (related to general and special responsibilities) and with the extent of the employee's contact with radioactive and fissionable materials. Employee instruction is provided by personnel knowledgeable in the various training topics.
)
Prior to assignment' to independent operation, each employee is required, by signature, to indicate that he has been instructed in radiation protection, criticality safety, and emergency response requirements and procedures.
auewoucNT amicanon one:
July 25,1990 11 52 ANF 3830.051 (6/89) 1
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4 ADMANCEDNUCLEAMMELS CORPORATION m p.2 l
SPECIAL NUCLEAR MATERIAL LICENSE NO. SNM.1227, NRC DOCKET NO. 701257 PART ll - SAFETY DEMONSTRATION REV.
26 l
?
p 11.5.2 Followup Training When changes are made to processes involving special nuclear materials,
[
radiation protection procedures, criticality safety controls (procedures, specifications, limits, etc.), fire protection or emergency response procedures, each employee affected is promptly infctmed and properly instructed by his/her manager or supervisor.
Additionally, each employee who routinely works with special nuclear material receives annual refresher instruction as part of Advanced Nuclear Fuels continuing program in radiation protection and criticality safety awareness. This training is provided
- by radiological and nuclear safety personnel knowledgeable in the various training topics.
[
l The effectiveness of this annual refresher training is determined by giving the employees l
a written examination and reviewing the correct answers to the questions at the end of l
the test.
All employees routinely discuss safety topics in monthly or quarterly scheduled safety meetings.
11.5.3 Emergency Response Trainina Training in operating plant fire extinguishers is offered to all employees on an annual basis.
i L
Plant Emergency Response Team members are offered training in incipient fire fighting techniques, advanced first ald, self-contained breathing apparatus in a smoke-filled environment, and radiological incident stabillzation techniques on an annual basis.
t Semi annual training is provided to all employees in the proper response to a j
criticality accident when a preannounced criticality evacuation drill is conducted.
11.6 Channes in Procedures, Facilities and Ee99 ment i
11.6.1 Facility and Eautoment Changes Changes in facilities and equipment involving licensed materials are accomplished through application of the Engineering Change Notice (ECN) procedure. This procedure provides the instructions for authorizing and documenting the Installation of new equipment, facilities, and services and mod!fications to existing equipment, facilities, and services.
Ie l
July 25,1990 11 53 i
ANF-3830.051 (G'89) t
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.s, i
ADn6NC8DNUCLEARPERLSCORPORATION gu p.g SPECIAL NUCLEAR MATERIAL LICENSE NO. SNM 1227, NRC DOCKET NO. 701257 REV-PART 11. SAFETY DEMONSTRATION 26 11.6.1.1 Scope included The ECN procedure is used when the work involved meets one or more of the following conditions:
Affects the basic principes of operation of the manufacturing process.
Directly involves fissile nistorial.
Affects criticality or radiological safety.
Impacts industrial healtn and safety.
Affects product quality.
Involves licensing matters.
Affects environmental protection.
Requires a process building wall penetration.
Requires underground work.
Affects manufacturing plant equipment layout.
Requires municipal building permit and/or fire marshall inspection.
11.6.1.2 Scope - Excluded ECN's tre not required for normal maintenance, repair or direct component replacement. ECN's are not required for minor changes which do not meet any of the above criteria.
11.6.2 Review Prior to preparation of an ECN, the drawings and scope packages are reviewed by a group made up of the responsible engineer, the Supervisor, Radiological and Industrial Safety, a representative of Plant Engineering and a representative of Operations.
l The group reviews the design package for industrial safety and health and radiological and criticality safety problems. Changes arising from the review are implemented prior to ECN routing. Verification of review and implementation of necessary changes is indicated by sign-off of the ECN by members of the review group.
aucwowtut amicatow oats.
July 25,1990 11 54 ANF.3830.05) (&89)
ADHSNCEDNUCLEAMMELS CORPORATION.
g.g SPECIAL NUCLEAR MATERIAL LICENSE NO SNM.1227, NRC DOCKET NO. 701257 PART ll SAFETY DEMONSTRATION REv.
26 11.6.3 Control / Documentation The ECN form, and any excavation or penetration forms included in the package, are edited for completeness and assigned a number by the Design and Drafting Clerk.
The ECN title and number is recorded in the ECN logbook and a permanent file established in the ECN record file.
11.6.4 Review / Concurrence / Approval The ECN receives approval by the User / Operator Manager. Prior to that approval, however, several other managers have reviewed and/or concurred with the package.
Following sign-off by the review group, the ECN package is routed in accordance with l
the Approval and Responsibility Matrix (Figure 12.3).
11.6.5 Execution f
Work begins upon receipt by either Maintenance or the Construction Engineer of copies of the fully approved ECN package issued by the Design and Drafting Clerk.
11.8.6 Acceptance For projects Delinvolving fissile material, acceptance of the work is documented by signatures of the Project Engineer, Plant Engineering, and the affected user manager.
l For projects involving fissile material, a physical review of the installation is made prior to introducing fissile material by a Criticality Safety Review Team consisting of the Criticality Safety Component and the Project Engineer.
The Supervisor, Radiological and Industrial Safety, documents the team's approval by signing the ECN formc 11.6.6.1 Startup Council
~
A separate overview of certain projects is provided by a Stanup Council prior to I
acceptance and operation of facilities, services and equipment which have incurred significant change. Projects requiring Startup Council review are-Those having impact on production.
Those with new safety issues or implications.
New major projects (facilities / operations),
i Others as determined by the Chairman.
auswowewt ameu:ow oaro July 25,1990 11 55 ANF.3830.051 (6/89)
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. J ADHSN'.MDMJCLEARPLELS CORPORATKW gu p.g SPECl4L NUCLEAR MATERIAL LICENSE NO. SNM 1227, NRC DOCKET NO. 701267 PART ll SAFETY DEMONSTRATION REV.
26 Membership of the Council consists of:
Chairman:
Manager,' Manufacturing Engineering l
Secretary:
Manager, Plant Engineering
'l At Large:
Manager, Plant Operations l
Manager, Safety, Security, and Ucensing Manager, Quality Assurance Manager, Plant Operations Manager, Materials ani Scheduling Manager, Process Engineering l
Responsible Operations Manager Startup Coordinator (usually Project Engineer) i Startup Council concurrence is required for system operation; however, final authority for approving actual startup rests with the responsible Operations Manager.
-t 11.6.6.2 Acceptance Test t
if an acceptance test is required prior to turnover of the facility, system or equipment to the operating group, acceptance of the work is accomplished via an
+
Acceptance Test Procedure (ATP), The ATP is signed off prior to performance by the responsible Engineer, the Manager, Plant Engineering, the Supervisor, Safety, the responsible engineer's manager, and the Manager, User Organization. Final acceptance f
is then documented by signatures of the responsible engineer, his/her manager, the Manager, Plant Engineering and the affected Operations manager.
11.6.7 Records The ECN record file is maintained by the Design and Drafting Clerk. Included in completed files are the original ECN's, a set of detailed drawings, specifications, applicable excavation and penetration permits, copy of any Criticality Safety Evaluation requests, and the completed ATP. Copies of saftty, hazard and criticality safety analysis are maintained by the Project Engineer and/or the person performing the analysis.
11.6.8 Procedure Changes The ECN procedure is prepared and maintained by the Manager, Plant l
Engineering, it is periodically reviewed for effectiveness and revised as necessary.
l ave =out=t amcues oats.
July 25,1990 11 56 ANF.3830.051 (6/89)
4. i g a
i ANF 2 Revision 26 Issue Date:
1 1 J
APPUCATION FOR RENEWAL OF SPECIAL NUCLEAR MATERIAL UCENSE NO. SNM 1227 l
(NRC DOCKET NO. 701257).
x l
DISTRIBUTION L A. Bisping C. W. Malody T. A. Bjernard
~J.
E. Pieper B. N. Femreite -
T. C. Probasco (4)
R. L Feuerbacher G. L Ritter E. L Foster I.
J. Samaritano R. G. Frain L J. Sevigny C. J. Francis J. R. Singleton.
J. W. Fredericks W. E. Stavig.-
L D. Gerrald.
l.
J. Urza J. L Glesener N. A. Vaught t
M. G. Hill C. J. Volmer W. V. Jackson USNRC/L. C. Rouse (6)
D. C, Lehfeldt DSHS/D. McBaugh (2)
Document Control (5) j 5-l l
4
- es+
---wei a
u