ML20082K494
| ML20082K494 | |
| Person / Time | |
|---|---|
| Site: | West Valley Demonstration Project |
| Issue date: | 06/28/1991 |
| From: | Dooley D, Faillace E WEST VALLEY NUCLEAR SERVICES CO., INC. |
| To: | |
| Shared Package | |
| ML20082K476 | List: |
| References | |
| REF-PROJ-M-32 WVNS-SAR-005, WVNS-SAR-005-R03, WVNS-SAR-5, WVNS-SAR-5-R3, NUDOCS 9108300074 | |
| Download: ML20082K494 (216) | |
Text
ATTACHMENT A s
j West Valley = ""'" ~ ^"- os Re vision Numter Demonstration Proj. ect 3 Revision Date Eng. Release #1435 Per ECN #3257 Per ECN #4353 SAFETY A..: LYSIS REPORT FOR LIQUID WASTE TREATMENT SYSTEM D. A. Dooley and E. R. Faillace Saf ety and Environment al Assessment July 1991 REQUIREMENT FOR ENVIRONMENTAL REVIEW MET BY REFERENCED DOCUMENT- W DP -O u 9 DATED December 1985 APPROVED HAZ ARD CLASSIFICATION : Low DATE OF APPROV AL: April 8, 1988 REFERENCED DOCUMENTS WD:35:0372 .
WD:35:0298 I DW: 38:0174 APPROVALS: bt T eb _t. G-z 2-9(
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West Valley Nuclear Services Co., Inc. i 1
P.O. Box 191 CAF0778 7RM West Valley, NY 14171-0191 WV-1816, Rev.1 910E:3noe ';; oln E:2.-
PD9 F'i 'J M~O2 PDR
l WNS - SAR-005 !
Rev. 3 -l RECORD OF REVISION i PROCEDLTE If there are changes to the procedure, the revision number increases by one.
These changes are indicated by placing a heavy vertical black line located in the right-hand margin adjacent to the sentence or paragraph which was revised.
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j Revision On Rev, No. Description of Changes Page(s) Dated l-l
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0 Original Issue All 1 Engineering Release #1435 2 Per ECN a4257 04/91
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3 Per ECN #4353 07/91 j i
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WNS SAR-005 Rev. 3 RECORD OF REVISION (CONTINUATION SHEET)
Revision on Rev. No. Description of Changes Page(s) Dated i
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I VEST VALLEY NUCLEAR SERVICES COMPANY DOCUMENT RELEASE FORM i i
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Docurnent No. : WNS -S AR-005 !
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Title:
LIQUID WASTE TREATMENT SYSTEM l f
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-I LIQUID WASTE TREATMENT SYSTEM l l
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l WNS - S AR- 005 Rev. 3, Draft D WEST VALLEY Di'.MONSTRATION PROJECT SAFETY ANALYSIS REPORT V0llRiE IV LIQUID WASTE TRIMTMENT SYSTFX TABLE OF CONTENTS Section Page LIST OF TABLES. . . . . . . . xi LIST OF FIGURES.... ... . . . . ..... xil LIST OF ACRONYMS AND ABBREVIATIONS. ... . . . . xv 11 . 1 . 0 INTRODUCTION AND GENERAL DESCRIYTION OF Tile FACILITY. . .. 1 H.1.1 Introduction. . . . . 1 H.l.2 Ger.cral Plant Description. .. . . 2 H.l.3 General Process Description. , . ... . . . . . ... 3 H.1.4 Identification of Agencies and Contractors. , . .. 4 H.1.5 Structure of this SAR. , 5
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SUMMARY
SAFETY ANALYSIS. , . 7 H.2.1 Site Analysis. , , ... .. 7 H.2.1.1 Natural Phenomena. 7 H.2.1.2 Site Characteristics Affecting the Safety Analysis. 7 H.2.1.3 Effect of Nearby Industrial. Transportation, and Military Facilities. 8 H.2.2 Radioloolcal Impact of Normal Operations. . ,,, 8 H.2.3 Radiological Impact from Abnormal Operations. . 9 H.2.4 Accidents. . . . 9 CAF0778:3PR - 1Li -
WVNS-SAR-005 Rev. 3, Draft-D TABLF. OF CONTENTS (CONTINUED)
- f Section Page H.2.5 Conclusions. .. . . ... ... .. . .... ........... ... 10 References for Section H.2.0...... . .... ...... ......... 11 H.3.0 SITE CHARACI' ERISTICS. . . . . , .................. ......... 12 H.3.1 CEOGRAPHY AND DEMOGRAPHY OF WVDP ENVIRONS.. .... . ....... 12 H.3.2 NEARBY INDUSTRIAL, TRANSPORTATION AND MILITARY FACILITIES. , 12 H.3.3 METEOROLOGY. ..... .. ... .. . ..... .. .. ........ 12 H.3.4 SURFACE HYDROLOGY.... . .. . . . . . . . ... .. 12 H.3.5 SUBSURFACE HYDROLOGY.. .. . . . .... ......... 12 H.3.6 GEOLOGY AND SEISMOLOGY. ... ........... . . . . .... 13 H.3.7 SITE ECOLOGY, , . . . . . . . 13 9
q H.4.0 PRINCIPAL DESIGN CRITERIA. . . .,. .. .14 V H.4.1 Purpose of the Liquid Waste Treatment System (LWTS) . . . ... 14 H.4.1.1 LWTS Functions. . .. . . . . ...... 14 H.4.1.2 Prime Feeds to the LWTS. . . . 14 H.4.1.3 LWTS Products and By-Products. .. ... .... ... , ..... 15 H.4.2 Structural and Mechanical Safety Criteria for the LWTS.. .. 15 H.4.3 Safety Protection Systems. . . . . .. .. 16 H.4.3.1 General.. .. . . .. . . ... . . . 16 H.4.3.2 Frotection by Multiple Confinement Barriers and Systems... 16 H.4.3.3 Protection by Equipment and Instrument Selection. . ....... 17 H.4.3.4 Nuclear Criticality Safety. . . . . . .. . . . . 17 H.4.3.5 Radiological Protection. . . . . . . ,. 17 H.4.3.6 Fire and Explosion Protection. , . .. . 18
() H.4.3.7 Radioactive Waste Handling and Storage. . . 18 CAF0778:3RM - Lv -
WVNS-SAR-005 Rev. 3, Draft D TABLE OF CONTENTS (CONTINUED)
Section Paf,e_
H.4.3.8 Industrial and Chemical Safety. . .. . .. . ..... 18 H.4.4 Classification of Structures, Components, and Systems.. . 19 H.4.5 Decontamination and Decommissioning. .. . .. . .. . ... 19 H.4.5.1 Lk'TS Construction. . . . .. .. .. . . .. 20 References for Section H.4.0. .. . 21 1
H.5.0 IVrS FACILITIES DESICN. . ... 25 H.5.1 Surmary Description of the Lk'TS . . 25 H.5 25 f ] 1 Location and Facility Layout. . . . .
H.5.1.2 Principal Features. . .... ... 25 H.5.2 Lk'TS Facilities . 25 H.5.2.1 Structural Specifications. . 25 H.5.2.1.1 Process Building Modifications. . . . 27 H 5.2.2 Lk'TS Layout . . 27 H.5.2.2.1 Radioactive Operations. 27 H.5.2.2,2 Nonradioactive Operations. 28 H 5.3 LWTS Support Systems. . . 28 H.S.3.1 Development of Support Requirements for Lk'TS . . 28 H.5.3.1.1 Cell Ventilation. 28 H.5.3.1.2 Emergency Power Requirements. . 29 H.S.3.1.3 Monitoring System (s). 29 H.5.4 Service and Utility System Descriptions. . 30 H.5.4.1 Process Building Heating and Ventilation System. . 30 H.5.4.2 Electrical. . . . 30 H.5.4.3 Compressed Air. . . . 30 H.5,4.4 Steam Supply and Distribution. 31 CAF0778:3RM -v-
WVNS-SAR-005 Rev. 3, Draft D TABLE OF CONTFNTS (CONTINUED)
O b Section he H.5.4.5~ Water Supply.. ....... .... ... ..... .. ...... .. .... . 31 H.5.4.6 Sewage Treatment., .. .. ... . ......................... 32 H.5.4,7 Safety Communications and Alarms. ............. ... ....... 32 H.S.4.8 Fire and Explosion Protection System...... .. ......... 32 H.5.4.9 Maintenance Systems. .... . ... . .... 33 H.5.4.10 Cold Chemical Systems. . . .. .. . . .. . 34 References for Section H.5.0. . . . . . . 35 H.6.0 LWTS PROCESS SYSTEMS. .. , ,, . ... . ... .. .. 37 i
H.6.1 Process Description... . . . . , . . 37 H.6.1.1 Narrative Description. . . . . , 37 H.6.1.1.1 Collection, Segregation and pH Adjustment. . . . . .. 37 H.6.1.1.2 Evaporation and Distillate Ion Exchange. . . .. . 38 H.6.1.1.3 Concentrates Collection and Transfer. . .. . 41 H.6.1.2 Flow Sheets. . . . . 41 H.6.1.2.1 Piping and Instrument Details. .. . . . 41 H,6.1.3 Identification of Items for Safety Concern. . 41 H.6.2 Process Chemistry and Physical Chemical Principles.. . . 42 H.6.3 Mechanical Process Systems. . . . ... 43 H.6.3.1 Cold Chemical Receiving. Handling and Transfer. . . of H.6.3.2 Feed Preparation and Handling. 43 H.6.4 Chemical Process Systems. .. . , .. . 43 H.6.4.1 Process Systems. 43 H.6.4.2 Component / Equipment Spares. . . . . . 43 I H.6.5 Process Support Systems. .. . .. .. .. . . 44 l
l H.6.5.1 Instrumentation and Control Systems. . . . .. . . 44 9AF0778:3RM - v1 -
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- WVNS-SAR-005 Rev. 3, Draft D g- TABLE OF CONTENTS (CONTINUED 1
. i 4 s Section Par.e H.6.5.2 System and Component Spares........... ......... .. ....... 45 H.6.6 LWTS Control Room............. .................. .. ...... 45 H.6.7 LVTS Sampling and Analytical Requirements and Procedures... 45 i References for Section H.6,0..... ........ ....... ....... 46 4
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! H.7.0 VASTE CONFINEMENT AND MANAGEMENT. . .., , .. . . . 47 1
j H.7.1 Waste Management Criteria. . . .... . . .. .. . . . 47 H.7,2 Radiological Wastes. .. . .... ... .. ... .. 48 Nonradiological Wastes.
H.7.3 . . . . . .... ....... 48 H 7.4 Off-Gas Treatment and Ventilation. .... . . ... .... 48 H.7.4.1 Operating Characteristics.. , , , , . . . . 48 H 7.4.2 Safety Criteria and Assurance.... .. .. . .... .... ..... 49
\ H.7.5 Liquid Waste Treatment and Retention. . ..... . .. .. . 49 H.7.6 Liquid Waste Solidification, . . . . . 49 H.7.7 Solid Wastes.. . . . . .. .. 50 References for Section H.7,0. . . . 51 H.8.0 RADIATION PROTECTION., . . ... ..... ... ... . . 52 H.8.1 Assuring that Occupational Radiation Exposures Are As Low As Reasonably Achievable (ALARA). . 52 H.8.1.1 Policy Considerations. . . . 52 H.8.1.2 Design Considerations. . . . . .. 52 H 8.1.3 Operational Considerations. . . . . ... . .. 54 H.8.2 Radiation Sources.. . . . . . . , . . 55 H.8.2.1 Contained Sources. . . . ... .. . . .. 55 H.8.2.2 Airborne Radioactive Material Sources. . . ... 56
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H.8.3 Radiation Protection Design Features. . .. . 57 CAF0778:3RM - vii -
WVNS-SAR-DOS Rev. 3, Draft D TABLE OF CONTE.NTS (CONTINUED) b V Section Page H.8.3.1 LWTS Design Features....... ... . . ....... ,. .........., 58 H.8.3.2 Shielding............ .. ... ... . .. . ......... ......... 58 H.8.3.3 Ventilation................ .... .. .......... . ........ 59 H.8.3.4 Area Radiation and Airborne Radioactivity Monitoring Instrumentation... . .... .... . . . . .. ..... . .. 60 H.8.3.5 Equipment and Process Decontamination Factors. . . 60 j H.8.4 Projected On-Site Dose Assessment. . , ... . . ..... .. 61 H.8.5 Health Physics Ptogram for LWTS.. .. . ... . . ....... 62 H.8.6 Off+ Site Dose Assessment, .. . .. . . . . . ..... 62 H.8.6.1 Effluent Monitoring Programs.. .. ... .. .. .. 63 j H.8.6.2 Analysis of Multiple Contribution. . . . . 63 i
H.8.6.3 Projected Doses From Airborne Releases. .. .... ... . 63 ,
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( H.8.6.4 Projected Doses From Liquid Releases. . . . ... ... . . 65 References for Section H.8.0. . , 67 H.9.0 INTS ACCIDENT SAFETY ANALYSIS. . 76 H.9.1 Abnormal Operations. . . .. . . ... 76 H.9.2 Abnormal Events - Prime Inputs to LWTS & Evaporator System 76 H.9.2.1 Failure of Tank 5D15B. . . .. . . .. .... 76 H.9.2.2 Evaporator Feed Pump (71-P-04) Falls. . . . 76 H 9.2.3 Loss of Evaporator Steam Supply. . .. 76 H.9.2.4 Loss of Electrical Power. . . . ...... 77 H.9.2.5 Loss of Evaporator Condenser Cooling Water. . .. 77 H.9.3 Abnormal Events - Process Support Equipment. . .. 77 H.9.3.1 Plugging of Concentrates Cooler. . . . 78 O
( j H.9.3.2 Evaporator Burps Its Contents (Eructation). . 78 CAF0778:3RM - viii -
WNS-SAR-005 Rev. 3, Draft D
! TABLE OF CONTFNTS (CONTINUED 1 Section Papi H.9.3.3 Overflow of Process Tanks and Equipment to Vessel Off-Gas. .. .. . .. . .. . . 78 H.9,3.4 Loss of Instrument Air / Utility Air. . .. . .. ... ... 79 H.9.4 Abnormal Events - Off-Gas Treatment... . . ... . 79 H.9.5 Abnormal Events - Ventilation System. . 79 H.9.6 Accidents. .. . .. . 80 H.9.6.1 Accidents Analyzed. .
.,. . 80 H.9.6.2 Source Terms. . . . . . 80 H.9.6.3 Off-Site Radiation Doses. . 81 H.9.6.4 Rupture of Process Line Between the Process Building and 01-14 Building. 82 H.9.6.5 Rupture of the LWTS Pipe Chase and/or the Pipe Chase Leaving the 01-14 Building. . .. 82 H.9.6.6 Process Tank Rupture Outside XC3. . 83 H.9.6.7 Tank Rupture Inside XC3, . . 84 H.9.6.0 V0G HEPA Filter Failure. 84 H.9.6.9 VOG HEPA Filter Fire. 85 H.9.6.10 Evaluation of Consequences of Anchor Bolt and Weld Failures Associated with LWTS Process Vessels. . . 86 H.9.6.11 Rupture of LWTS Transfer Pipe and Spill of Evaporator Cleaning Solution. 88 H.9.7 Minor Accidents. 89 H 9.8 Potential for Nuclear Criticality. 89 H. 9.8.1 Evaporator Acid Wash. . 90 References for Section H.9.0. . . 92 H.10.0 CONDUCT OF IVIS OPERATIONS. 112 H.10.1 Organizational Structure. 112 CAF0778:3RM - ix - i
WNS-SAR-005 Re v . 3, Draft D TABI.E OF CONTENTS (CONCllIDED1 Section Page H,10.2 Preoperational Testing and operation.. . .. 112 H.10.2.1 Administrative Procedures for Conducting the Test Program.. 112 H.10.2.2 Test Program Description. . .. . . . .. . . 112 H.10.2.2.1 Physical Facilities. . . . . . 113 H.10.2.2.2 Process Operations. 113 H.10.2.3 Test Discussion. 114 H.10.3 Training Programs. . .. 114 H.10.3.1 Scope, Objectives, and Coals of the Lk'TS Operator Qualification Program. . .. 114 H.10.3.2 Operation Prerequisites. . . . 115 H.10.3.3 Training Resources. 116 H.10.3.4 Training Content Outline. 117 H.10.3.5 Qualification Verification / Documentation. .., . . . 118 H.10.3.5.1 Examinations. . 118 H.10.3.5.2 Documentation. 119 H.10.3.5.3 Quality Assurance. 119 H.10.3.6 Requalification. . . . 119 H.10.4 Normal Lk'TS operations . . . 121 H.10.4.1 Lk'TS Procedures . . , 121 References for Section H.10.0. 122 H.11.0 OPERATIONAL SAFFTY REQUIREMENTS. . .. 123 H.12.0 QUALITY ASSURANCE. . 124 H.12.1 Quality Assurance Program. 124 H.12.2 Implementation. 124 References for Section H.12.0. 127 CAF0778:3RM - x-
WVNS-SAR-005 Rev. 3, Draft D VOLUME IV f
\' " LIST OF TABLES Number Title Page H.1.5-1 Current (1990) Structure of the West Valley Demonstration Proj ect Safety Analysis Report. . . . . . . . .................. 6 F.4.1-1 Radionuclide Inventory (1991) of Decontaminated First Sludge Wash.... .... , ,. . . 22 H.4.1-2 Projected Activity in Waste Streams to be Processed by LWTS.... . ... , . . . 23 H.4.4 1 Safety and Service Classification of Important Structures, Components., and Systems Associated with the Liquid Waste Treatment System. ..... ... ... ... 24 H.5.3 1 LWTS Utility Requirements. .. .. . . . . . .. 36 l H.8.2-1 LWTS Weste Stream Feed. . .. . 68 L
H.8.2-2 Projected Radionuclide Inventory in Tank 8D-2 Decontaminated Sludge Washes (1991) Processed by LWTS... 69 H 8.3-1 Results of LWTS Shielding Analysis... . . ... 70 H.8.3-2 Equipment and Process Decontamination Factors. . 71 I ,
I H.8,6-1 Projected Plant Stack Discharge From Waste Streams to be Processed by LWTS.
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L H.8.6-2 Collective and Maximum Individual Doses Predicted l From Stack Releases Resulting From Routine Operation !
of LWTS. .. .. .. .. ... . 73 H.8.6-3 Comparison of Maximum Airborne Concentrations of Selected Nuclides at Site Boundary With Current
- l. DOE Derived Concentration Guides (DCC).. . 74 l
l H.8.6-4 Collective and Maximum Individual Doses Predicted l From Liquid Pathway Releases From Processing Sludge Washes Through LWTS. .. . . . .. . . .. 75 l
H.9.1-1 Potential Abnormal Events for LWTS Subsystems or Major Process Components. . .. . .. . 94 H.9.1-2 LWTS Tank Volumes and Secondary Containment. . .. 103
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t H.9.6-1 Dose to the Maximally Exposed Of f-Site Individual
\- for the Significant Radionuclides from the Evaporation of Evaporator Concentrates Associated with Rupture of Process Line. . . . 104 CAF0778:3RM - xi -
UVNS-SAR-005 Rev. 3. Draft D VOLUME IV LIST OF TABLES (CONCLUDED)
Number Title Par.e H.9.6-2 Dose to the Maximally Exposed Off-Site Individual for Significant Radionuclides from the Evaporation of Decontaminated Supernatant Associated with Rupture of Process Line in the New LWTS Pipe Chase (120' el).... 105 H.9.6-3 Dose to the Maximally Exposed Off-Site Individual for the Significant Radionuclides from the Evaporation of Evaporator Concentrates (50 pCi/mL Cs-137) for a Tank Rupture outside XC3. .. .. . . . ... . 106 H,9.6-4 Dose to the Maximally Exposed Off-Site Individual for the Significant Radionuclides from the Evaporation of Liquid from Spent Zeolite Resin to the Floor of XC3. . 107 H.9.6-5 Dose to the Maximally Exposed Off-Site Individual for the Significant Radionuclides for a HEPA Filter Failure Accident. . ... . . . . . .. 108 H.9.6-6 Dose to the Maximally Exposef Off-Site Individual for the Significant Radionuclides for a HEPA Filter Fire Accident. .. . . . . . 109 H.9.6-7 Dose to the Maximally Exposed Off-Site Individual for the Significant Radionuclides Evaporated from a Spill of Evaporator Cleaning Solution Following Rupture of Transfer Pipe. . .. 110 _
H.9.8-1 Maximum Concentrations of Fissile Material in LWTS l Evaporator Concentrates. . . .. 111 H.12.1-1 Quality Levels of Important Structures, Components, and Systems Associated with the Liquid Waste Treatment System. . . 128 O
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VVNS-SAR-DOS Rev. 3, Draft D i
V0lllME IV LIST OF FIGURES H.1,3 1 Primary LWTS Process Flowpcth H.4.1-1 Process Diagram - LWTS - 901D-020S1, Rev. 1 l t
H.4.1-2 Process Diagram - LWTS - 901D 020S2, Rev. O H.4.1-3 Process Diagram - LWTS - 901D-020S3, Rev. 0 ,
H.L.1-4 Process Diagram - LWTS - 901D 020S4, Rev. O j H.5.1-1 WVDP Site Plan - 900E-1988, Rev. O H.S.1-2 Key Plan Process Building (Bechtel 15R-H 1, Rev. 3) '
H.S.2-1 General Arrangement LWTS Plan El, 100.00' - 901D-041, Rev. 2 H.5.2-2 General Arrangement LWTS Plan El. 114.50' - 901D-042, Rev. 0 l l
H.5.2-3 General Arrangement LWTS Plan El. 131.00' - 901D-043, Rev. 2 !
H.5.2-4 General Arrangement LWTS Plan El. 144.00' - 901D-044, Rev. 0 ,
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) H.5.2-5 General Arrangement LWTS Plan El. 160.00' - 901D 045, Rev. 0 r
H.5.2-6 General Arrangement LWTS Sections - 901D-046, Rev. 1 H.5,2-7 General Arrangement LWTS Sections - 901D-047, Rev. 0 ,
H.6.1-1 P&ID LWTS - 901D-021S1, Rev. 10 !
l l- H.6.1-2 P&ID LWTS - 901D-021S2, Rev. 4 l
l H.6.1-3 P&ID LWTS -
901D-021S3, Rev. 2 H.6.1-4 P&ID LWTS - 901D-021S4, Rev. 0 5 l H.6.1-5 P6ID LWTS - 901D 021S5, Rev. 0 ,
i H.6.1-6 P&ID LWTS - 901D-02156, Rev. 1 {
H,6.1-7 P&ID LWTS 901D-02157, Rev. O I H.6.1-8 P&ID LWTS - 901D-022, Rev. 14 H.6.1-9 P&ID LWTS - 901D-023S1, Rev. 9 ;
l H.6.1-10 P&ID LWTS - 901D-02352, Rev. 9 l !
H.6.1-11 P&ID LWTS - 901D-023S3, Rev. 3 '
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WVNS-SAR-005 Rsv. 3, Draft D t
VOLUME IV A
LIST OF FIGURES (CONCLUDED)
H.6.1-12 P&ID LWTS - 901D 024, Rev. 15 H.6.1-13 P&ID LWTS - 901D 026, Rev. 9 H 6.1-14 P&ID LWTS - 901D-049, Rev. 9 H.6.1-15 P&ID LWTS -
901D-050. Rev. 5 H 6.1-16 P&ID LWTS - 901D-051, Rev. 4 H.6.1-17 P&ID LWTS - 901D 059, Rev. 10 H.6.5-1 LWTS Control Panel Outline Drawing - 901D-395, Rev. 1 H.6.5-2 LWTS Control Panel - Front View Layout - 901D-396, Rev. 11 H,6.6-1 LWTS Control Room General Arrangement - 900D-1180, Rev. 4 I
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WVNS-SAR-005 Rav. 3, Draft D
, V011JME IV
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LIST OF ACRONYMS AND ABBREVIATIONS ALARA As Los As Reasonably Achievable C Centi, Prefix for 10-2 "C Degree: Celsius CAA Cell Access Aisle i CAM Continuous Air Monitor CEDE Committed Effective Dose Equivalent CRT Cathode Ray Tube CSS Cement Solidification System D&D Decontamination and Decommiss!oning DCG Derived Concentration Cuides DOE Department of Energy DOP Dioctylphthalate DOT Department of Transportation AP Delta Pressure (pressure drop) 4 EPA Environmental frotection Agency r
( FCV Flow Control Valve GCR General Purpose Cell Crane Room I
COA Ceneral Purpose Cell Operating Aisle j HF _'A High Efficiency Particulate Air :
HNO 3 Nitric Acid HTDS High Total Dissolved Solids HV Heating / Ventilation IWP Industrial Work Permit kW Kilowatt i
!. LCV Level Control Valve I LLWTF Low Level Waste Treatment Faci.lity (02 plant)
! LTDS Low Total Dissolved Solids LWA Lower Warm Equipment Aisle LWC Liquid Waste Cell LWTS Liquid Waste Treatment System LXA Lower Extraction Aisle l u Micro, Prefix for 10-6 m Meter m Milli, Prefix for 10'3 MCC Motor Control Center CAF0778:3RM - xv -
p WVNS SAR.005 Rev. 3 Drcit D i r
V0WME IV LIST OF ACRONYMS AND ABBRIN1ATIONS }
(CONCIEDED)
Na0ll Sodium Hydroxide !
NRC Nucicar Regulatory Commission ]
f OJT On the Job Training ;
OSR Operational Safety Requir ment i i
P&lD Piping and Instrument Dirgram !
PCR Process Chemical Room l PLC Programmable Logic Contrc,ller ;
PPC Product Purification Cell ;
psi Pounds Per Square Inch e psig Pounds Per Square Inch Gauge !
ppm Parts Per Million RWP Radiation Vork Permit .
SAR Safety Analysis Report !
SPDES State Pollutant Discharge Elimination System ;
(New York State Permit)
STS Supernatant Treatment System TDS Total Dissolved Solids U1h Uranium Londout f UFC Uranium Product Cell !
UWA Upper Warm Aisle t UXA Upper Extraction Aisle VOC Vassel Off Cas VF Vitrification Facility i w/o Weight Percent ;
WVDP West Valley Demonstration Project l WVNS West Valley Nuclear Services Company I Incorporated ;
i XCR Extraction Chemical Room i XC3 Extraction Cell 3 ,
Extraction Sample Aisle ;
XSA I
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CAF0778:3RM xvi -
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WNS SAR 005 ;
Rev. 3, Draft D l l
t O 11 . 1 . 0 INTRODUCTION AND GENFRAL DESCR11710N OF Tile FACILITY l
i 11 . 1 . 1 INTRODUCTION i
This Safety Analysis Report (SAR), WNS SAR 005, Volume IV, Part 11, Liquid
{
Waste Treatment System (LWTS), was prepared to meet the requirements of the i U.S. Department of Energy (DOE) Order DOE 5481.1B (U.S. DOE,1986), Idaho f Operations Office (ID) Order ID 5481.1A (U.S. DOE ID, 1989), and Vest Valley !
Nuclear Services Co., Inc. (WNS) Policy and Procedure W-906, Rev. 8 (WNS, j 19w0). Further introductory information relating to the WDP Act, ancillary f tasks and supporting activities that aust be accomplished may be obtained from [
Section A.1.1 of Volume I of the Project SAR (WNS-SAR-001), f i
?
Former PUREX reprocessing activities generated high-level radioactive waste
{
(HLW) that is stored in Tank 8D 2. This llLW is separated into an alkaline
[
supernatant and sludre. It is the task of the WDP to convert the llLW into berosilicate glass for ultimate storage in a federal repository. (The prelt.minary SAR for the Vitrification Facility (VF), in which the llLW will be !
converted into borosilicate glass, is WNS SAR-003) . In order to accomplish th*s mission pretrer.cment of the HLW is necessary, i i
The pretreatment is performed by the Sludge Mobilization and Wash System (SMVS), analyzed in WNS SAR-004, Volume III, Part D, and the Integrated [
Radwaste Treatment System (IRTS) which consists of the STS, also analyzed in !
WNS SAR 004; the Liquid Waste Treatment System (LWTS), described and analyzed
! in this SAR; the Cement Solidification System (CSS), described and analyzed in i WNS SAR-008, Volume IV, Part C: and the Drum Cell (DC), described and i analyzed in WNS-SAR-007, Volume IV, Part K.
The LWfS was operated from 1988 through 1990 to process the decontaminated .
supernatant produced by STS (see Revision 1 of this SAR). This revision of the LVTS SAR is an update to focus on the next HLW processing step. ;
1 i CAF0778:3RM 1 [
1 !
_ ._._m.- _ . _ _ _ _ _ _ . . _ _ __ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _
WNS SAR 005 Rev. 3, Draft D l l
The SMWS will remove the interstitial salts and salt crystals f rom the PUREX sludge. This will be accomplished in four cycles by mobilizing the sludge ,
1 with the sludge mobilt:ation pumps and using dilute caustic solution to l suppress actinide solubility while dissolving the salt and salt crystals. The wash solution will then be treated by ion exchange in Tank 8D 1 to remove most l of the cesium, strontium and plutonium. The washed sludge will be stored in I Tank 8D 2 until it is used as melter feed to the VF. l 1
The LWTS will then process the decontaminated sludge wash solutions by evaporation. The LWTS product consists of a concentt ted solution that will be sent to CSS for incorporation in a cement matrix. ,- part of this process, the LWTS will produce airborne and liquid effluents in a form suitable for j discharge to the environment, l l
l In the future, LWTS will also be used to process radioactive 11gulds in j l
support of the vitrification facility and in final plant decontamination.
l 1
- 11. 1 . 2 CENERAL PLANT DESCRII" TION The UVDp site is located in a rural setting approximately 50 km (30 mi) south of Buffalo, New York, an average elevation of 400 m (1,300 ft) on New York !
State's western plateau. The plant facilities used by the VVDP occupy ;
approximately 63 hectares (156 acres) of chain link fenced area within a 1,350 hectares (3,300 acres) reservation that constitutes the Western New York Nuclear Service Center (WNYNSC). The communities of West Valley, Riceville, Ashford liollow and the village of Springville are located within 8 km (5 mi) of the plant. Several roads and one railway pass through the site, but no human habitation, hunting, fishing or public access is permitted on the WNYNSC.
The major LWTS process components are located in cells inside the main process building of the former nuclear fuel reprocessing facility (Figure H.5.1-1 and H.5.1 2). The liquid feed tank, 50 15B, and the concentrate collection tanks, ,
SD-15A1/A2, are located in the Uranium Product Cell (UPC). The major ,
components of the system, the evaporator and distillate ion exchange columns, ;
CAF0778:3RM 2 i
_ - . - _ - .-..._._-s . . . - _ , _ . . . - ~ _ . - - _ , , _ . _ - , _ . . _ . . , . . - , - _ _ _ , , _ - . , _ . _ . _ , . . . . . . . . - - . . , _ , . , . - _ _ - , . _ , . _ . _ , , -
VVNS SAR 005 i Rev. 3, Draft D I i
are located in the Extraction Cell 3 (XC3). LVTS interfaces with STS/SWMS by receiving liquids from Tank 8D 3. LWTS product is sent co CSS through the ;
Vaate Dispensing Vessel (WDV). The LWTS control room is shared with CSS and l is located in the 01 14 building.
f
.i i
There are several important design considerations to ensure the safety of the j system. These are described in detail in Section H.8.1.2. The most important I are that the process vessels and cells are maintained under negative pressure, i that structural barriers have been designed such that the confinement of .
i liquid radioactive waste will not be compromised by any credible design basis l r
event, and that redundancy in critical aspects of the operation is used. An j example of the redundant nature of the operation is the ventilation systems. }
Botu of the ventilation systems used by the LW*S contains redundant I ventilation trains and are connected to emergency backup power.
Additional design conr.iderations can be found in Section H.4.0. Operationni l 4
considerations are maintained by administrative and procedural control as i i
described in Section H.8.1.3. Also, Operational Safety Requiremen*ts (OSRs) j and Technical Requirements (TRs) are presented in Volume VI, Part M.11 of the f Project SAR. f i
H.1.3 CENERAL PROCESS DESCRIPTION f f
r A simplified description of the overall WVDP activities is presented in Section A.1.3 of Volume I and includes those processes required for HLW handling and vitrification. The LWTS process pre nted in this volume will i provide the means to concentrate liquids such that a cemented waste form can f
be produced in the CSS facility.
i Figure H.1.3 1 illustrates the primary process flowpath for LWTS liquids. The
{
LWTS process is fully automated and is controlled from the LWTS control f room. Decontaminated sludge wash solution is transferred from Tank 8D-3 (the !
t SMWS product tank) to Tank 5D-15B (the 15,000 gallon ISTS feed tank) by means of pump P-01. Pump P-4 transfers the liquid from Tank 50 15B to the high ;
efficiency evaporator /rebo11er 31017, which is run in thermosyphon mode. The I i
CAF0778:3RM 3 f t
l l t I
.._.,-.-,,,___._.I
i WNS.SAR 005 l Rev. 3, Draft D l distillate from the cow;cnker is processed through a zeolite ion exchange column to remove cesium and strontium. This liquid effluent is then sent to the low level liquid wasce treatment facility (LLVTF) for additional treatment prior to discharge to the environment. Cascous effluents from the evaporation process are collected by the Vessel Off.Cas (V0G) system, HEPA filtered, and discharged through the main plant stack. The concentrates produced in the evaporator are pulled through a concentrates cooler E.005 by pump P.16 and fed to T ek 5D.15A1 or 5D-15A2. The concentrates are then transferred to the CSS Waste Dispensing Vessel. Instrumentation placed at strategic points throughout the system allow the process parameters to be monitored from the LVTS control room in real time. Feed and product tanks, as well as effluent points can be sampled to ensure that the liquid waste stream is within the process parameters.
l The LVTS was designed to allow sufficient flexibility so that i f one flow path l 1
were temporarily down for maintenance, the process could be re-routed along an l alternate path.
The LVTS was originally designed to include a low dissolved solids liquid treatment subsystem to provide recycle water for other LVTS processes. The process and instrumentation diagrams in this SAR illustrate the low TDS and recycle water subsyatems. Most of the equipment was installed but is not currently operr.tional. The impacts of operating this equipment will be analyzed in a revision to this SAR if, and when, this equipment becomes operational.
11 , 1 . 4 IDENTIFICATION OF AGENTS AND CONTRAC'It)RS SectJon A.1.4 of Volume I identities the agents and contractors responsible
- or : implementing the WDP. The relationships between VVNS and agents and contractors is illustrated in Figure A.1.4 1 of Volume I, i . .
CAF0778:3RM 4 ,
i 1 l
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WNS.SAR 005 Rev. 3. Draft D 11 . 1 . 5 STRUCTURE OF Tills SAR The concept of this modular SAR is explained in Section A.1.5 of Volume 1.
The structure of the SAR is patterned after NRC Regulatory Guide 3.26. See the Table of Contents, which reflects this pattern.
Since it was published as Table A.1.5 1 of Volume I in June, 1985, the format of the WDP SAR has evolved as required by changes in Project milestones. As originally conceived, sludge mobilization, washing and transfer of all HLV (loaded zeolite THOREX and washed sludge) was to be included in Part E, Volume III, " Sludge Mobilization System (SMS)". Because of revisions to the Project schedule, it has not been feasible to follow the original outline for the Project SAR (Table A.1.5 1) . The current plan is to issue a separate module, Part E of Volume Ill, to cover the llLV transfer operations. A copy of the current structure of the Project SAR is provided in Table H.1.51 and will be added to Volume I during the scheduled rautine update. Structural changes in response to revisions in Project milestones are anticipated.
O O
CAF0778:3RM 5
WVNS SAR 005 Rev. 3. Draft D
[ ') TABLE 11.1. 5 - 1 Q CURRENT (1990) STRUCTURE OF Tile WEST VALLEY DEMONSTRATION PROJECT SAFETY ANALYSIS R570RT WVNS SAR Volume Title Part Desir. nation I Project Overview and General Informatior A 001 II Existing Plant cnd Operations B 002 III liigh-Level Waste Vitrification o Vitrification Facility l C TBD 3
o Supernatant Treatment System2 D 004 o SMS and itLW Transfer E TBD IV Waste Management, Storage and Disposal o High-Level Waste Interim Storage F TBD o Cercent Solidification System C 008
[ ; o Liquid Waste Treatment System 11 005 o Size Reduction Facility I 010 o Lag Storage Facility J 009 o Disposal Area Operations K 006 6 007 V Final Decontamination, Decommissioning L TED and Waste Shipment VI Operational Safety Requirements M NA l
l Notes:
l d
j l'.'4SARs for the Vitrification Facility (Part C) and liigh Level Waste Interim i Storage (Part F) to be combined into one document.
- 2. Includes a revision for the Sludge Mobilization and Wash System (m)
G'
- 3. Preliminary SAR for the Vitrification Facility is SAR-003 CAF0778 : 3PJi 6
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i VVNS SAR 005 Rev. 3, Draft D l I
I
- 11. 2 . 0
SUMMARY
SAFTTY ANALYSlfi This Safety Analysis Report (SAR) was prepared to address safety issues I associated with the operation of the Liquid Waste Treatment System (LUTS).
The purpose of LVTS is to process radioactive liquid wast
- to reduce liquid waste volume, and to provide feeds to the Cement Solidifi .lon System (CSS) or return concentrates to the High Level Vaste Tank Farm (VTF). This module of the Project SAR is limited to the construction and operation of LWTS. LW5 interfaces to CSS, the VF, and the Supernatant Treatment System (STS) are also discussed. ,
The LWTS originally described in this report included a recycle water subsystem; however, as of May 1991 this subsystem had not been installed, and there are no current plans for installation. This safety analysis encompasses operation of the LVTS without the recycle option.
The following sections summarize the radiological impacts of LVTS operations. No on site or off site releases of hazardous chemicals in excess of TLVs are anticipated under normal operations or accident conditions,
- 11. 2 . 1 SITE ANALYSIS i
- 11. 2 . 1 . 1 NATURAL l' LID 40MENA See Section A.2.1.1 of Volume I.
- 11. 2 . 1 . 2 SITE CllARACTERISTICS AFTECTING Tile SAFFTY ANALYSIS The majority of components of the LVTS associated with the processing of radioactive wastes are located in Extraction Cell 3 (XC3). Other components are located in the Uranium Product Cell (UPC), Uranium Loadout (ULO) area, and the Product Purification Cell (PPC) as well as throughout the site (e.g.,
interceptors, in-ground tanks, etc.). Accidents are analyzed !.n Section H.9,6 for process equipment and other components which support LVTS operation. The release of radioactivity from these accidents could be direct or indirect. A CAF0778:3RM 7
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VVNS SAR 005 Rev. 3, Draft D
() direct release may involve a spill or a leak outside the confines of the LVTS piping or ventilation system which results in area contamination, release of airborno activity or evaporation of liquids to the atmosphere. An indirect release occurs when all material from a spill can be contained by structures and ventilation with subsequent release from established discharge points.
The Process Building is part of the Main Plant ani is at an elevation well above flood potential. Natural phenomena (earthtuake, tornadoes, high winds, and snow loading) are accounted for in accidents where these cenditions may have an impact. Seismic phenomena in particular may be initiating events for some of the accidents analyzed in Section 11.9.6.
11 . 2 . 1 . 3 E}TECT OF NF.ARBY INDUSTRIAL, TRANSPORTATION, AND MILITARY FACILITIES See Section A.2.1.3 of Volume I.
- 11. 2 . 2 RAD 10lIX ICAl, IMPACT OF NORMAL. OPERATIONS O
U Both on site and off site dose assessments were performed in order to determine the radiological impact of normal operations (Section H.8.0). The dose to on site personnel is due to work in areas of elevated radiation levels relative to background. The maximum annual collective occupational dose was estimated to be 16. 5 person rem (Section 11.8.4) . 6.5 for operations and 10 person rem for maintenance activities.
A liquid and an airborne pathway were considered to estimate off-site doses.
The Main Plant Stack is the airborne pathway release point and the lagoon system is considered for the normal liquid pathway (see Sections 11.8.6.3 and
- 11. 8. 6 . 4 ) . AIRDOS EPA (an atmospheric dispersion code) was used to estimate the atmospheric transport and diffusion of radioactive particulates. Site specific meteorological data was used in combination with AIRDOS-EPA to estimate the dose to off-site individuals. The maximum dose to an individual from routine airborne releases was estimated to be 3.7E-03 mrem. For the liquid pathway, conservative assumptions lead to a predicted maximum individual off site dose of 0.21 mrem for the period when the Tank 8D-2 sludge wash solutions are being processed.
CAF0778:3RM 8
M M .SAR-005 Rev. 3, Draft D
- 11. 2 . 3 R_ADIOllX;ICAl. IMPACT FROM AliNORMAL OPFRAT1,0NS Abnormal operations are events which could occur from malfunctions of systems, operating conditions, or operator error. Abnormal events are only of consequence for those systems in the LWTS which process, control, or confine radioactivity. The abnormal events considered (Section H.9.2 through 5) are of little consequence in terms of potential for environmental releases.
On site and off-site impacts, if any, to individuals from such abnormal operations will be minor and in all cases bounded by the accident analyses, 11 . 2 . 4 ACCIDEWrS Seven accidents associated with the LWTS were analyzed (Section 9.6).
Accidents analyzed include ruptures of various process lines. a tank rupture inside and outside XC3, High Efficiency Particulate Air (HEPA) filter failure, HEPA filter fire for the Vessel Off Gas (VOC) System and the Main Plant Ventilation System, and a spill of evaporator cleaning solution following a pipe rupture. Releases are assumed to be direct to atmosphere for the various pipe ruptures, while all other releases are from the Main Plant Stack. Doses from these accidents to the maximally exposed off-site individual for the two precess line ruptures are 42 and 0.45 mrem, respectively. The maximally exposerl on site individual is estimated to receive doses of 750 and 8.1 arem, respectively, from these ground level releases. The difference between the two accidents concerns the type of material being handled and quantity of material released. For the tank rupture outside XC3 (5D15A1 in UPC), the dose is calculated as 4.1 E-03 mrem. Analysis of a tank rupture accident inside XC3 (Spent Zeolite Tank, 71 D 007) leads to a predicted dose of 4.8 E-07 mrem to the maximally exposed off-site individual. The dose to the ma::imally exposed off site individual for the V0G System HEPA failure is 0.34 mrem while the HEPA fire dose is projected to be an order of magnitude higher at 3.4 l
mrem. The dose for a failure of or fire in the Main Plant Ventilation HEPAs is considered to be the same as or less than that for the VOC HEPAs. The dose from a spill of evaporator cleaning solution following the rupture of a transfer pipe is calculated as 120 mrem to the maximally exposed off site individual and 2.2 rem to the maximally exposed on-site individual.
CAF0778:3RM 9
i WNS SAR 005 l Rev. 3. Draft D [
I Due to the batch mode of IRTS operations, accidents in the STS will not affect i 1RTS (other than delay operations). Strailarly, accidents originating in INTS f will not have a direct impact on CSS and Drum Cell operations. l i
P 11 , 2 , 5 CONCil!SIONS
(
l This Safety Analysis Report was prepared to treet the requirements of DOE Order 5481.1B and DOE ID Order 5481.1A, " Safety Analysis and Review System" (USDOE, j 1986a, and USDOE, 1989) and WNS Policy and Procedure W 906, " Safety Review Program." The analyses were performed in accordance with DOE Order 5480.5, !
" Safety of Nuclear Facilities" (USDOE, 1986b) and DOE Order 5480,10, i
" Contractor Industrial slygiene prograrn" (USDOE, 1985). The analysis !
dernonstrates that the facility can be operated safely. The facility has been f designed to minimize radiological hazards to members of the public and project !
reaff by reducing the amount of waste in the process at any one time f commansurate with process requirernents and by conducting operations remotely f within a sealed, shieldeci cell. The analyses contained herein predict no [
\ :
doses of consequence to either on-site or off-site individuals as a result of l normal operations or accidents. Conservative assumptions lead to an estimated f l collective dose to workers of 16.5 person rem / year for normal operations. (
Calculated doses to the ma::Imally exposed off site individual were determined f
for both normal and accident conditions. All doses under normal operating f conditions are within the requirements of DOE Order 5400.5 (USDOE, 1990). All f accidents analyzed are enveloped by the criteria for a low hazard facility in f DOE ID Order 5481.1A (USDOE, 1989).
f l
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CAF0778:3RM 10 !
7 WNS SAR 005 Rev. 3. Draft D R_ETHENCES mR_SEcr10N 11.? ,0 US DOE, 1989, DOE-ID Order 5481.1A, " Safety Analysis and Review System," dated April 11, 1989.
US DOE, 1990, DOE Order 5400.$, " Radiation Protection of the Pubile and the Envi ronroe nt , " dated June 5, 1990.
US DOE, 1985, DOE Order 5480.10 " Contractor Industrial llygiene Program,"
dated June 26, 1985.
US DOE, 1986a, DOE Order 5481.1B, " Safety Analysis and Review System," dated September 23, 1986.
US DOE,1986b, DOE Order 5480.5, " Safety of Nuclear Facilities," dated September 23, 1986.
O l
O CAF0778:3RM 11
WNS.SAR 005 i Rev. 3, Draft D 11.3.0 SITE CllARACTERISTICS Site characteristics potentially affecting the WDP as a whole are detailed in Volume 1 Section A.3. Site characteristics affecting the LVTS are described below.
11 . 3 . 1 CEOCRAlifY AND Dl'MOCRAI1IY OF WDP ENVI*tDNS See Section A.3.1 of Volume I for a general site discussion. There is no effect on LVTS operations from geography and demography of WDP environs,
- 11. 3 . 2 NEARBY INDUSTRIAL,_ TRANSPORTATION AND Mll.ITARY FACIL1TIF.S See Section A.3.2 of Volume I for a general site discussion. There is no effect on LVTS operations as a result of these site characteristics, 11 . 3 . 3 MITEOR0lIX.*Y O See Section A.3.3 of Volume I for a general discussion of meteorology around the WDP. Meterological site characteristics did not af fect the LVTS design.
11 . 3 . 4 SURFACE IlYDROIDGY See Section A.3.4 of Volume I for a gener:t1 discussion of surface hydrology around the WDP. Surface hydrology characteristics did not affect the LVTS design.
11 . 3 . 5 SUBSURFACE IIYDROIDGY See Section A.3.5 of Volume I for a general discussion of subsurface hydrology around the WDP. Subsurface hydrology characteristics did not impact the LVTS l design.
L i
l O ,
V CAF0778:3RM 12
. . _ . _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ . _ . . _ . . . . _ _ _ _ _ _ _ _ . . _ _ _ _ _ _ . = _ _ . _ . . . . _ _ _
WNS SAR 005 Rev. 3, Draft D j i
i 11 . 3 . 6 CEoIIL'Y AND SEISM 0!IL'Y ;
a See Section A.3.6 of Volume I for a general site discussion. Site seismic l criteria were used in both the or1 61nsi design of the process building as well !
as structural modifications of the process building to incorporate the ISTS.
i
- 11. 3 . 7 SITE EC011L'Y See Section A.3.7 of Volume I for a general discussion. There is no effect on the LVTS operation as a result of sitn ecology. !
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WNS SAR.005 [
Rev. 3, Draft D j i
11 . 4 . 0 l'RINCIPAL DESIGN CRITERI A 11 . 4 . 1 PURPOSE OF Tile LIQUID WASTE TREA'INENT SYSTEM (1MTS) !
The main purpose of the LWTS is to process low level liquid radioactive waste j generated as a result of various WDP activities for eventual solidifcation in -
cement. Activities expected to provide the largest amount of liquid to be ;
processed include decontarnination of SD. ' supernatant, sludge washing, operation of the vitrification melter feed concentrator, and various plant ,
. decontamination efforts. LWTS will concentrate liquid wastes into a minimum !
I volume consistent with process requirements, principally by evaporation and ;
i ion exchange, and ttansfer evaporator concentrates to CSS for solidification in cement. '
11 . 4 . 1 . 1 1Yr5 MINCr10NS i
The LWTS performs the following functions: ,
l o Reduces the volume of liquid radioactive wastes received consistent l with process requi rernents , !
o Provides a means to coordinate movettent and storage of liquid wastes between WDP processing systems.
11 . 4 . 1 . 2 PRIME FEFDS TO Tile IMTS f f
Until the end of 1990 decontaminated supernatant from the STS was the primary !
feed to the LWTS via Tank $D15B. Four 8D-2 sludge washes will be the next l
l feed to LWTS (Table 11.4.1-1) . Two other irnportant feeds to LWTS are the ;
overheads from the melter feed concentrator and decontamina::lon wastes. Any .
l feed material requiring pit adjustroent prior to evaporation or other treattnent '
will be adjusted with acid or caustic solutions as necessary. Table 11.4.1- 2
(. shows the origin of future LWTS feed sources and the activity (curies) ;
associated with each stream. It should be noted that LWTS will process !
I approximately 50% of the activjty requiring disposal (see DOE /EA-0295).
CAF0778:3RM 14 !
r i
r.,_... _, . _. , , . . _ . - . ,. - . . _ . , _ _ -
WNS SAR 005 Rev. 3, Draft D Figures H.4.1-1 through 11.4.1-4 contain the process flow diagrams for LVTS operation. Detailed information on vaste streams expected ~o be processed by LVTS are contained in Saha (1986).
11 . 4 . 1 . 3 IXTS PRGOUCTS AND BY-PRODUCTS If products of LWTS operaticn are considered to be those materials whier are either sent to the WTF, CSS, or to surface discharge, the LWTS will then produce two identifiable products from its operation. These products are:
- 1) evaporator concentrates (to CSS or VTF), and 2) evaporator distillate for surface discharge.
By-products include the following radioactive or radioactively contaminated materials:
o Samples drawn from the system for analysis o Spent HEPA and other filter media o Ion exchange resins o Equipment or materials which are repaired or replaced o Materials used for personnel protection during operations, maintenance, and radiation protection activities.
o Decontamination and Decommissioning (D&D) wastes o Liquids from sumps and flocr drains o Spent eveporator cleaning solutions 11 . 4 . 2 STRUCTURAL AND MEC11ANICAL CAFT.TY CRITERIA FUR Tile IVrS, I
The majority of LWTS components are installed in existing structures such as XC3, PPC, ULO, and UFC. All existing structures have been analyzed for structural and mechanical safety in the NFS SAR and WDP SAR, Volumes I and II (NFS, 1962 and WVDP, 1985a). Those documents contain the safety criteria applied in the design of the LWTS. Minor modifications of structural materials necessary to accommodate LVTS piping and equipment in the Process Building are not considered significant enough to change the overall CAF0778:3RM 15
WVNS SAR 005 Rev. 3, Draft D
() structural safety in the above mentioned analysis.
associated with a loss of structural integrity are minor when LWTS is compared Furthermore, the hazards to previous reprocessing activities. The only structure which can be considered as new is the concrete below-ground trench which serves as a pipe chase between Tank 35104 and LWTS. Seismic analysis of the trench was not considered necessary due to the relatively small quantity of activity present at any one time, or the short time required to transfer evaporator acid wash solution (Sections H.9.6.5 and 11.9.6.11) .
11 . 4 . 3 SA5'E"!T PROTECTION SYSTEMS 11 . 4 . 3 . 1 GENERAL LWTS has been designed to meet all applicable engineering codes and standards in effect at the time of construction, installation, and system startup (WVDP, 1985b). Specific information regarding the varinus types of safety protection systems considered necessary for the operation of LWTS appear below.
O 11 . 4 . 3 . 2 PROTECTION BY MULTIPLE CONFINEMENT HARRIERS AND SYSTEMS Tho primary confinement barrier for the relatively low concentration of radioactive materials processed by LWTS operations is considered to be the system piping, tankage, and associated process vessels. Secondary confinement is afforded by XC3 which houses the heart of the LWTS system, the high efficiency waste evaporator, and the ion exchange columns.
The Process Building, which houses XC3, acts as tertiary confinement. Vented tanks and process vessels within the Process Building will have potentially contaminated air contained by the existing V0G System prior to release.
The major cells used by LWTS, UPC and XC3 are equipped with stainless steel liners and sumps. Sump levels are checked once per shift. The operability of the sump high level alarms is check quarterly. In addition, the transfer pipe trench is designed to drain into a sump.
O CAF0778:3RM 16
- . , . . , , . , . . . . . . - , . , - , ..-_-, . . - - , - . w.. -- . . - . . ,
WNS SAR 005 Rev. 3, Draft D l
All confinernent and containtnent barriers have been designed to limit potential releases of radioactive material in accordance with generally accepted As Low As Reasonably Achievable ( A1 ARA) prac tices in compliance with the latest revision of WDP 010, " Radiological Controls Manual."
- 11. 4 . 3 . 3 PROTECTION BY U}UIPMENT AND INSTRUMDrf SEIEffl0N Procurement of equipment and instrumentation for operation of the 1.VIS was done in compliance with VVNS' Quality Assurance prograta which is described in Section 12 of Volume I (WDP 1985a) . The quality levels of the individual systems and components for LVTS are given in Table H.12.1 1. Current requirements for new equipment and modification to existing equipment are given in Section 11.12.0.
Existing equipment and instrweentation placed in service was subjected to inspection and testing commensurate with its intended use.
Process instrumentation was designed to provide the primary indication of off-standard operating conditions. This instrumentation provides an indication and alarm under abnorrtal operating conditions.
- 11. 4 . 3 . 4 NUCISAR CRITICALITY sal'ETY A nuclear criticality is not considered a credlble event for the types of processes associated with ISTS operation (see Sec tion 11. 9. 8 ) . Therefore, criteria which address nuclear criticality safety have not been included in the original system design.
11.4.3.5 RADIGIDCICAL PROTEL710N Construction and maintenance activities are performed in accordance with WD P - 010, " Radiological Controls Manual." Shield walls, confinement and containment structures as well as administrative controls (procedures, training, Operational Safety Requirements [0SRs), etc.) are used as necessary to maintain radiation doses to occupationally exposed personnel AIARA.
CAF0778:3P3 17
I WNS SAR 005 ;
Rev. 3, Draft D I i
O Protective clothing (anti C's, respiratory protection) is worn when required U by radiological conditions. In addition, precautions such as system decontamination and flushing are required in the case of necessary contact ,
maintenance. [
t 11 . 4 . 3 . 6 FIRE AND DtPiDSION PROTECTION ;
I The LVTS has fire dete ction equipm. int, alarm systerns, and suppression systems i cormnensurate with potential fire hazards associated with LWTS operation as [
determined by the WNS Radiation and Safety group. Fire and explosion hazards are eval ated in accordance with the WNS Industrial Hygiene and Safety Manual I (WDP 011) and TR GP-16. These are discussed in Section 11.5.4.8.
11 . 4 . 3 . 7 RADIDACTIVE WASTE IIANDLING AND STORAGE I
LWTS operations use a number of existing tanks to temporarily store LWTS feed
{
material and process material in different stages of the operation. Storage !
of these liquid materials in any one process vessel or tank is considered to !
i be a temporary condition. Bounding consequences of failures and ruptures of i various LWTS tanks are considered in Sections 11. 9. 2.1, !! . 9. 6. 6 and 11. 9. 6. 7. ;
f
- 11. 4 . 3 . 8 (NDUSTRIAL AND CilEMICAL SAFETY !
i The WNS Industrial Hygiene and Safety Manual, WDP 011, provides the i administrative guidelines and control over industrial and chemical safety in j regard to the operation of LVTS. While currently not in use, the LWTS process provides for addition of acid or caustic to feed solutions. Analysis of an i accident where acid and caustic are inadvertently mixed is considered in '[
Section H.9.7. Analysis of an accident where an acid cleaning solution is !
t spilled is considered in secticn H 9.6.11. i f
i t
I CAF0778:3RM 18 I h
r+ - -- = * - - - * - . =
l WVNS SAR 005 i Fev. 3, Draft D l
( 11.4.4 CIASSIFICATION OF STRUCTURES, COMI'ONDTTS __3 AND SYSTDtS :
L i Sdftty and SBTVice Classifications of ittportant structures, components, and S
systema associated with the LWTS are presented in Table 11.4.4-1. The procedures and criteria used to arrive at the designated classifications are contained in Section A.4.4 of Volume 1.
Accident analysis (Section 11. 9. 6) shows that no postulated accident will result in a dose to the maximally exposed off site individual approaching 500 mrem. Therefore, no items need to be classified as Safety Class A or B.
The heating / ventilation (liv) supports, vessel off gas piping, and ventilation :
instrumentation and alarms are classified as Safety Class C. The llV suppotts and V0G piping are Class C because they ensure confinement of radioactivity.
The instrumentation and alarres for ventilation systems are considered Class C because their loss of function could allow unroonit ored releases. Likewise, airborne particulate and area radiation monitors are Class C due to the ,
potential for unmonitored releases should failure occur.
N Sump piping, instrumentation, and alarms are Class C for reasons of confinement of radioactive material and because loss of instrumentation and alarms could lead to undetected leakage and potential ior inadvertent exposure :
) (see also Section H.4.3,2). All other items are Safety Classified as N.
- 11. 4 . 5 DECONTAMINATION AND DECOMMISSIONING Specifications for LWTS equipment and components which will contain i
radioactive material call for stainless steel (types 304, 304L, 316, 316L).
l This will allow periodic flushing of the system with strong decontamination agents, thus removing the maximum amount of deposited radioactive material.
As a result, personnel dose will be minimized during the decommissioning effort. It must be recognized that the LWTS system would most likely be the last of the VVDP systems to be dismantled due to the key role it plays in vaste water management.
s
\ i CAF0778 : 3PJi 19 l
l t
WVNS SAR-005 Rev. 3, Draft D ;
, Decontamination and decommissioning of LWTS will probably take place in a ;
\
manner similar to the initial D&D of XC3, PPC and other areas of the plant.
The methods used are likely to result in similar personnel doses for LVTS D&D, Hazards associated with this type of work are addressed in Volume II.
H 4.5.1 IRTS CONSTRUCTION A Safety Analysis has been writ:en to support the Phase I construction effort
[
of LVTS (Ploetz, 1986a). It concludes that the initial phase of work is i
covered by the existing Safety Analysis for decontamination and l decommissioning contained in Volume II.
To support all future phases of LWTS construction a Hazard Classification and an Environmental Checklist were prepared (Ploetz, 1986b, 1986c). In I accordance with the criteria of WVNS Policy and Procedure WV 906 and DOE ID '
Order 5481.1, LWTS construction meets the criteria of a low hazard activity.
The Environmental Checklist demonstrates that enginaering controls will maintain proper ventilation for all construction activities. Liquid and solid
(} waste generated by LWTS construction will be properly handled, stored and disposed.
All LWTS construction activity was performed using approved procedures and in accordance with VVDP-010 " Radiological Controls Manual" and WVDP 011
" Industrial Hygiene and Safety Manual."
l I
O CAF0778:3RM 20 l
f
WVNS.SAR.005 Rev. 3, Draft D 1
4 REFERENCES }X)R SECTION 11.4.0 l
- Letter WD
- 86:0804, Rykken, L. E., to W. W. Bixby, " Referenced Radionuclide Content of High Level Waste." dated November 10, 1986.
Memo HH:86:0056, A. K. Saha to Distribution, "RTS Waste Stream D:.ta Sheets, j Rev. 4," dated March 27, 1986.
- Nuclear Fuel Services, 1962, Final Safety Analysis Report, Volumes I through IV, Revision 0 through 4.
Ploetz, D. K., 1986a, Letter HH:86:0057, D. K. Ploetz to J . L. Knabenschuh,
" Revised Safety Analysis for Construction of LWTS Phase I."
Ploetz , D. K. , 1986b , Lette r AD: 86 :0027 Technical Director to J. L. Knabenschuh, " Revised Hazard Classification for Construction of LWTS."
~
Ploetz, D. K. ,1986c , Letter HH: 8o:0049, D. Y,. Ploetz to C. J . Roberts ,
" Environmental Checklist for Construction of the Liquid Waste Treatment System."
West Valley Demonstration Project, 1985a, Safety Analysis Report, Volumes I and II, Revision O.
Vest Valley Demonstration Project, 1985b, Environmental Evaluation for the Liquid Waste Treatment System, WVDP 049, Revision O.
West Valley Demonstration Project, 1985c, Safety Analysis Report, Volume IV, Cement Solidification System, Revision O.
US' DOE, DOE /EA-0295, Environmental Assessment for Disposal of Project Low-Level Waste, West Valley Demonstration Project, Part 1: Environmental Assessment, April 1986.
CAF0778:3RM 21
e WNS-SAR 005 I Rev. 3 Draft D l
()
TABLE 11.4.1-1 ;
RADIONUCLIDE INVENTORY (1991) 0F DECOKTAMINATED FIRST SilIDGE WASilII) i Radionuclide _h0"f"fbikeE" ^bbhhs7(2) t 11 3 1.26 E 05 2.51 E+01 ,
C-14 2.22 E 05 4.43 E+01 l Fe-55 1.92 E 08 3.84 E 02 [
Co-60 1.99 E 06 3.99 E+00 :
Ni-63 1.38 E-04 2.76 E402 .
Sr 90 1.13 E 04 2.26 E+02 '
Y 90 1.13 E 04 2.26 E+02 Tc-99 2.36 E-04 5.13 E+02 i Ru-106 1.40 E 07 2.81 E 01 !
Sb-125 3.62 E 05 7.24 E+01 I Te 125m 8.12 E.06 1.62 E+0). '
1-129 3,40 E-08 6.80 E-02 Cs-134 4.09 E 0'/ 8.18 E 01 '
Cs 137 8.19 E 04 1.64 E+03 ;
f s, Ba.137m 7.75 f. 04 1.55 E+03 1 Pm 147- 1.18 E 05 2. 36 E401
'Q Sm-151 2.29 E-07 4.58 E-01 Eu 154 2.07 E 06 4.14 E+00 Eu-155 2.81 E 07 5.61 E-01 U 233 9.60 E 07 1,92 E+00 !
U 234 5.76 E 07 1.15 E+00 i U-235 1.26 E 08 2.51 E-02 I U 238 1.18 E-07 2.36 E-01 !
Pu-238 3.10 E 05 6.20 E401 '
Pu-239 6.00 E 06 1.20 E+01 <
Pu 240 4.52 E-06 9.05 E+00 Pu-241 2.95 E 04 5.89 E+02 .
l Am-241 5.17 E 06 1.03 E+01 I Am 243 3.69 E-07 7.39 E-01 Cm-244 1.48 E-06 2.95 E+00 '
l TOTALS 2.66 E 03 5. 31 E+03 (1) Derived from Tabel D.8.2-2 of STS SAR assuming DF - 8 for Pu, DF - 5 for Sr, DF - 1000 fer Cs, and 1:1 dilution with water.
(2) Based on 2 E+06 liters. ,
l CAF0778:3RM 22 l
l
_ . ~ . - _ . . - - . - - . . . . - . _ - -
r WNS SAR 005 I Rev. 3, Draft D '
l TABLE 11.4.142 T IVITY IN VASTE STREAMS TO BE l'ROCESSED BY 12TS IA)
PROJECTED AC. j I
i Activity ,
Vaste Stream _I,C,u rie s ) !
8D-2 Decontaminated Supernatant Processed from 1988 l to 1990 ,
First Sludge Wash 5.31 E403 l Second Sludge Wash 1,60 E+03 Third Sludge Wash 4.19 E402 i Fourth Sludge Wash 1.09 E+02 l Decon of Plant Cells 6.4 E+02 Helter Feed Concentrator Overheads (2) TBD Spent Zeolite Slurry 7.76 E+00 ;
Filter Backwash 2.43 E+02 TOTAL 8.33 E+03 (1) Sludge wash activities derived from Table D-8.2-2 of the STS SAR, all i
others derived from Waste Stream Data Sheets, Saha (1986) and Rykken i' (1986).
(2) This stream will be returned to the Waste Tank Farm for eventual encapsulation in glass and is not included in the column total.
k i
l I O
CAF0778:3RM 23
)
VVNS SAR 005 Rev. 3, Draft D TABl.E 11. 4 . 4 - 1 SA} TTY AND SERVICE CLASS 1FICATION OF IMI'ORTANT STRUCTURES, COMPONFRTS, AND SYSTIMS ASSOCIATED WIT!! Tile LIQUID WASTE TRFATMENT SYSTIM SAFETY SERVICE COMPONENT OR SYSTEM CLASS CLASS STRUCTURES Existing Process Building (Modified) N III Shield walls (New) N III Maintenance access doors and hatches N III Air lock doors N IV Stainless steel liner N IV Sumps and associated drainage lines N IV Floor drains and lines N IV Pipe supports N .a 1 Conduit supports N IV Heating /Ver.tilation supports C III Pump vault N III Valve pit N III WASTE PROCESSING Collection tanks and associated piping N IV Evaporator, condenser, and coolers N III Filter N III Iop Exchangers N III O Solids hold tanks Liquid feed tanks Concentrate tanks N
N N
III III IV Interceptor N IV Recycle water tanks N IV Atmospheric release evaporator N IV PIPING Process piping N III Vessel off gas piping C III Utility piping N IV Instrument piping N III Sump piping C III ELECTRICAL POWER SYSTEMS Motor control centers N IV Conduits, cables, and supports N IV Motors N IV INSTRUMENTATION AND MONITORING SYSTEMS Process instrumentation and controls N IV Ventilation instrumentation and t.larms C I I '.
Sump instrumentation and alarms C III Airborne particulate monitors G lli Area radiation monitora C III O
CAF0778:3RM 24
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/-~
\s-11 . 5 . 0 LVTS FACILITIES DESIGN 4
- 11. 5 . 1
SUMMARY
DESCRIPTION OF Tile INTS i
!!.5.1.1 IDCATION AND FACILITY IAYOUT .
t The majority of LWTS process equipment is located in XC3 of the Process Building. Figure 11.5.1-1 shows the layout of the VVDP facilities, with the Process Building located in the approximate center of the former NFS [
complex. Figure H.5.1-2, taken from Volume II of the SAR, is specifically [
marked to show those areas of the Process Building which are used to house equipment associated with LWTS operation. It should be noted that a number of I existing tanks located throughout the facility are used to support liquid r transfer and temporary storage for LWTS operation. They are identified by the .
word " existing" and by dashed lines in the process flow diagrams in fL Section H 6.0. .
i 11 . 5 . 1 . 2 PRINCIPAL FEATURES '
Principal features of the site are contained in Section B.5.1.2 (Volume II).
i Main Plant Systems provide utilities such as electrical power, compressed air, steam and water (see Section H.5.4). The high total dissolved solids system along with the high efficiency waste evaporator are located in XC3, All '
system controls are located in a control room outside the 01-14 Building at ;
the 100' elevation.
11 . 5 . 2 IWrS FACILITIES 11 . 5 . 2 . 1 STRUCTURAL SPECIFICATIONS Structural requirements for LWTS meet the pressures and temperatures as
() specified in the process flow diagrams, Figure H.4.1 1 through H.4.1 4.
process components meet the structural requirements of ANSI A58.1, while the All l
CAF0778:3RM 25
- - - -__~ .- _ - . _ . . . . . _ - _ . . - - - . _ . .- - . - _ - . . , - . -
d WNS SAR 005 Rev, 3. Draft D i
structural aspects of the process building are covered under the New York
, State Building Code. Material requirements for LWTS equipment is listed in WNS (1986) and will not be repeated in this document.
, The existing main process building and modifications made to incorporate the LVIS have been designed and built to UBC Zone II seismic criteria. The results of seismic analyses are summarized in Section B.S.2.1.1 of Volume II of the WDP SAR.
. Exteriors of components installed indoors but not inside cells are capable of enduring-the following ambient design conditions for at least ten years:
1 o Pressure 0 to -5 cm (-2 inches) water column gauge !
relative to atmosphere o Temperature 15 - 35 C o Atmosphere Air with 30 to 100 percent relative humidity Components potentially exposed to ambient weather are capable of enduring the following additional design conditions for 10 years:
o Temperature -40 C to 35 C o Wind Load 155 kilometers per hour l o Snow Load 176 kg/m 2 o Rain 75 cm/yr The exterior of components installed inside cells are capable of withstanding the following ambient design conditions for at least 10 years:
o Pressure O to -5 cm (-2 inches) water column gauge relative to atmosphere o Temperature 15 -49 C o Atmosphere air with 30-100 percent relative humidity o Total Integrated Dose 106 rad W
J CAF0778:3RM 26
WVNS SAR 005 Rev. 3, Draft D 11 . 5 . 2 . 1 , 1 Process Building Modifications Upon completion of decontamination and decommissioning efforta in XC3, minor modifications were made to the cell to support placement of LWTS process equipment. Numerour aall penetrations were made between XC3 and the PPC to accommodate the placement of the valve gallery outside of XC3. This provides for valve maintenance in a relatively low exposure rate stea compared to the XC3 environment. Other minor modifications were raide in PPC for valve galler*;
support, installation of pumph and equipment in ULO and UWA, installation of the ion exchange hopper and filter backwash skid in the Extraction Chemical Room (XCR), as well as modifications made to LXA, the lower Warm Equipment Aisle (LWA), Upper Extraction Aisle (UXA) and Process Chemical Room (PCR).
11 . 5 . 2 . 2 IRTS LAYOITT The general layout of LWTS components, associated piping and systems are shown on the general arrangement drawings, Figurer. H . 5. 2 - 1 through Figures 11. 5. 2 - 7.
11 . 5 . 2 . 2 . 1 Radioactive Operations The majority of LWTS radioactive operations are confined to XC3 where the bulk of the process equipment is located. Ilowever, many other locations such as PPC, ULO, UPC and areas of the site which contain storage or transfer tankage can also be considered a part of radioactive operation. All areas within the main process building where LWTS process components exist are maintained under slightly negative pressure by either the VOC System or Main Plant Ventilation (see Section H.5.4.1). Sump jets exist in all areas of the Process Building where LWTS operates. Sumps deliver any spilled liquid to holding tanks to allow for proper processing (e.g., sampling and treatment).
The LWTS evaporator can accept radioactive feed f rom Tank 35104 using Pump 71-P-01, or Tank 5D15B using Pump 71-P-04. Concentrates from the evaporator exit the Process Building and flow to the 01-14 Building, feeding the CSS Waste Dispensing Vessel. All waste streams from the zeolite columns either return to CAF0778:3RM 27
WVNS.SAR-005 Rev. 3, Draft D
(}
s_;
LWTS for further processing or are routed to the LLWTF (02 Plant) for discharge via the Lagoon system. Melter feed concentrator overheads will be returned to the WTF af ter concentration by LWTS.
H.5.2.2.2 Nonradioactive Operations Two areas exist where LWTS nonradioactive operations occur. The first is in the XCR, which contains the ion exchange fill hopper (71 D-004) and the filter !
backflush skid and associated components. The second is the Chemical Feed '
System located in LXA. Nitric acid (HNO )3 and sodium hydroxide (NaOH) storage tanks with separate positive displacement pumps and associated equipment are the major components of this system. These areas are serviced by Main Plant ,
Ventilation and maintained under slightly negative pressure- The LWTS Control Room can also be considered as part of nonradioactive operations.
11 . 5 . 3 IRTS SUPPORT SYSTEMS !
/~ Table H.S.31 presents an overview of utility service required for LWTS
\
operation.
- 11. 5 . 3 . 1 DEVEIDPMENT OF SUPPORT RF4UIREMENTS EUR LWTS
- 11. 5 . 3 . 1 . 1 Cell Ventilation i
! The Main Ventilation System is the primary source of ventilation for XC3 and 1
i other areas which contain LWTS process equipment within the Process Building. The Main Ventilation System description and operational characteristics are contained in Volume II, Section B.S.4.1 of the West Valley Demonstration Project (WVDP) SAR.
l CAF0778:3RM 28 l
VVNS-SAR 005 Rev. 3, Draft D 11 . 5 . 3 . 1 . 2 Emergency Power Requirements LWTS Process Systems are not supplied with auxiliary power. The system is designed to fail safe upon loss of electrical power,
- 11. 5 . 3 . 1 . 3 Monitoring System (s)
LWTS is a well instrumented process system. Remote sensing capability is required due to the radiation exposure rates and the degree of contamination associated with most of the LWTS components and equipment. Under normal conditions, all LWTS pump motors and valves, with the exception of block valves at cell walls and maintenance drain valves, can be operated remotely from the LWTS control panel, Process tanks contain level instrumentation with indications (annunciations) and alarms at appropriate levels. Some process tanks also contain stream density instrumentation. Other parts of the LWTS are outfitted with sensors for flow, temperature, radiation and pressure at appropriate locations for proper process control.
Monitoring systems important to safety are listed in Table H.9.1-1. These include:
o Tank high- and low-level alarms o Sump high-level alarms o Density controllers o Evaporator high- and low-level alarms o Feed line stream flow interlocks o Evaporator high density alarm o Level, pressure, radioactivity, and flow indicators on tanks and/or transfer pipes o Evaporator high radiation alarm o Filter high differential pressure alarm o Stack monitor indication / alarm o Alarm on lack of airflow through damper
\ CAF0778:3RM 29 a
l WVNS-SAR 005 Rev. 3 Draft D .
P\
( j' 11 . 5 . 4 SERVICE AND UTILITY SYSTEM DESCRII"I' IONS 11 . 5 . 4 . 1 PROCESS BUIIBING llEATING t" VENTIIATIOti SYSTEM '
Process Building HV needs are provided by the plant Main Ventilation System (Section B.S.4, Volume II). Briefly, those areas having the lowest concentrations of 4,irborne activity (e.g., the control room, stairways, I analytical aisles, etc.) are supplied fresh filtered, conditioned air at an average rate of ten air changes per hour, on a once through basis. Areas of higher concentrations of airborne activity such as operating aisles and laboratories are maintained at an approximate negative 0.025 kPa WC. The warm aisles and sample aisles are maintained at approximately -0.075 kPa WC. This '
air is exhausted through a filter train consisting of a prefilter and absolute [
filter prior to exhaust out the main stack. Areas where contamination is ,
least expected are maintained as contamination-free as possible by the ,
increasing negative pressure requirements engineered into the main plant ,
I g ventilation system. ;
i s .
l 11 . 5 . 4 . 2 ELECTRICAI. '
a Primary, secondary and emergency power are described in Section B.5.4.2.1 of 'i Volume II of the SAR. LWTS is supplied with a normal 45 kW of power with 460 volt 3 phase or 120 volt single phase capability. Peak power demand is rated at 75 kW.
- 11. 5 . 4 . 3 COKPRESSED AIR t
Most valves and level instrumentation in LWTS require a compressed air supply for operation. Utility and instrument air are supplied as shown in the following table:
P h
4 CAF0778:3RM 30 k
WVNS SAR-005 Rev. 3, Draft D i
Litres / Min Utility Air Pressure (kPa) Temperature ( C)
Peak 689 32 C (max) 2800*
Normal 689 32 C (max) 560*
Instrument Air 334 and 138 32 C (-34 C 1160 Dew Point)
- Rated flow at 27 C, 689 kPa LWTS is designed to fail safe in the event of loss of compressed air supply.
The fail-safe position of valves (i.e., either open or closed) is indicated on the Piping and Instrument Diagrams (P& ids). The Air Supply System is described in detail in Section B.5.4.3 of Volume II. All valves in radioactive service fail closed to stop transfers of waste streams.
H.5.4.4 STEAM SUPPIX AND DIS *hRIBUTION Steam supply for LWTS originates from the Plant Steam Supply System discussed in Section B.S.4.4 of Volume 11. Saturated steam is supplied at high (1034 kPa) or low (172 kPa) pressure. The 'maj or purpose of the steam supply is to provide the heat source for the high efficiency waste evaporator. In addition, a number of steam eductors located throughout the system are required for opera
- ion.
11 . 5 . 4 . 5 UATER SUPPLY Section B.S.4.5 of Volume 11 describes the Plant Water Supply System and the Plant Demineralized Water Systems. The Plant Water Supply System which includes demineralized water and cooling tower water supplies seal water for various pumps and cooling water to the evaporator condenser and concentrates cooler. Demineralized water is also supplied as flush water to the new CAF0778:3RM 31 i i
WNS SAR 005 Rev. 3, Draft D Chemical Feed System and to the lon Exchange Fill System. Under normal conditions cooling water is supplied at 946 litres / min, and domineralized water at 20 litres / minute. Under peak conditions cooling water is supplied at 1200 litres / min and demineralized water at 150 litres / minute. Possible consequences of 16 sing cooling water supply are discussed in Section 11.9,0, 11 . 5 . 4 . 6 SENACE TREATMENT Facilities are available for use in the Main Process Building by LWTS operations Personnel, 11 . 5 . 4 . 7 SAFETY COMMUNICATIONS AND ALARMS The LkTS Control Panel is equipped with a graphic display and a system of indicators (annunciators) and alarms to indicate abnormal or undesirable process conditions. LWTS System logic is controlled using a Programmable Logic Controller (PLC). LkTS Operations Personnel have telephone communications available to STS Operations Control. LWTS and CSS Operations Persot.nel share a common control room. LWTS instrumentation and controls exist such that the system may be safely operated, monitored and shut down from a central point, the LWTS Control Room. Many automatic systems are able to be manually overridden in the event of off-normal conditions or failure to operate properly. Other off-normal conditions have to be corrected before continuing action can be taken. The plant telephone system "all page (222)"
is used for external communication. The "all page" system number 812 is for emergency use only.
- 11. 5 . 4 . 8 FIRE AND FXPLOSION PROTECTION SYSTEM There is no potential for explosion in the LWTS. The LWTS is equipped with fire detection equipment, alarm systems, and suppression systems commensurate with its needs as determined by the West Valley Nuclear Services Company, Incorporated (WNS) Radiation and Safety Croup. Fire fighting procedures for LWTS conform to existing WNS procedures and TR-Cp-16.
CAF0778:3RM 32
WVNS-SAR-005 ?
Rev. 3, Draft D !
l' A
The only identifiable potential fire hazards in the LWTS System are electrical ;
insulation, oil-used for pump and other equipment lubrication, and the organic ,
ion exchange resin system. Mixing of concentrated acid and caustic (not [
currently performed) is capable of producing temperatures sufficient to ignite !
t flammable material; however, the event is considered unlikely XC3 and other ,
areas where LWTS components are housed are constructed of cone. ate and !
steel, All LWTS process components are manufactured from nonflammable ;
materials, Nonc. of the above mentioned potential fire hazards are considered -
to be a high-risk hazard. Due to the Icw potential fire hazard in the process [
cells during LWTS operations, these are not equipped with fire detection and f
protection equipment, The LVTS control room is equipped with a wet pipe f
sprinkler system. The LWTS control panels are equipped with fire detectors ;
and halon extinguisher. l H.5.4.9 MAINTENANCE SYSTEMS [
t
\
LWTS systems and components are installed in decontam!nated process cells (
(XC3, PPC, etc.) and have a design life of ten (10) years. Equipment such aa ;
I valves, pumps, and instrumentation which may require periodic servicing or I
repair are designed to be remotely flushed with clean water prior to contact ;
maintenance. Where possible, these components are located away from high f
j radiation sources to reduce potential exposure to personnel from other process !
l components. Piping, valves, and pumps are designed to be self-draining to the >
l l maximum extent possible. Most valves within XC3 which are located in high i
(
l exposure rate areas are equipped with remote manual operators in the event of actuator failure or malfunction.
i All maintenance work is performed in accordance with WVDP-010 " Radiological ,
Controls Manual" and WVDP-011 " Industrial Health and Safety Manual," In the operational phase, ALARA is maintained by having the ability to flush lines, and by placement of components which may require repair or servicing in " low" f exposure rate areas. Temporary shielding is also used to support maintenance f activities. f CAF0778:3RM 33 [
i F
l f
WNS SAR.005 Rev. 3, Draft D 11 . 5 . 4 . 1 0 COLD CIIEMICAL SYSTEMS A chemical feed system is located in LXA. It consists of storage tanks and positive displacement pumps to feed acid (llNO3 ) or caustic (NaOH) as needed to support processing of waste streams. Demineralized water is available to flush process lines of residual acid or caustic. The Chemical Feed System has aie ability to add :cid or caustic to Tai.Ls 7D-2, SD15A1, SD15A2 and SD15B.
Potential abnormal events and accidents coticerning the system are addressed in Section H.9.7.
CAF0778:3RM 34
I WNS SAR 005 Rev. 3, Draft D O
'd REFERDiCES FOR SECTION H.5.0 American National Standards Institute, A58.1, 1982, Minimum Design Load for Buildings and Structures.
WNS , 1986, Design Criteria for the Liquid Waste Treatment System, Rev. 1, Trat}smitted by Memo WD:36:0267.
O O
l l
l l
CAF0778:3RM 35
P WNS-SAR-005 Rev. 3, Draft D TABI.E 11. S . 3-1 IvrS UTII.ITY REQUIREMENTS Electrical ,kW 480Vu 34 120V, 1p
?
Normal 45 X X Peak 75 X X 1
Emergency 45 NA NA Rated Flow Rate Compressed Air Temperature Pressure (psig) (litres / min)
Utility, normal 27 C 100 560 '
l Utility, peak 27 C 100 2800 {
Instrument 27 C 50 1160 '
Emergency NA 0 0 i
Steam Supply Saturated Pressure (kPa) !
. 'J Low Pressure X 172 ;
High Pressure X 1034 i Emergency NA 0 '
Demineralized Water Flow Rate (litres / min) ,
Normal 20 Peak 150 Emergency 0 Cooling Water (AT - 5.5 C1 Flow Rate (litres / min) i i Normal 946 Peak 1200 l Emergency 0 ,
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. VVNS SAR 005 Rev. 3. Draf'c D 11 . 6 , 0 LVTS PROCESS _, SYSTEMS 11 . 6 . 1 PROCESS DE3CR11'rION The Liquid Waste Treatment System consists of processing equipment., valves, pumps, instruments, piping and controls which are required to transfer and process various ifquid wastes consistent rith the other Project Process Systems (CSS and VF, WVDP, 1985a and 19855). The heart of the LWTS Process System is a high efficiency waste evaporator which reduces the volume of water in the various types of liquid waste processed. Liquid effluents (evaporator overheads) produced by LWTS are pre-treated by ion exchange prior to transfer to the 02 plant.LVr5 is a strategic system in that it receives and processes varioe.s liquid wastes and provides feed to CSS. In addition, LWTS is designed to provide for limited st.rge capecities and temporary storage of liquid waste an necessary. The following acetions describe the LWTS in detail .
11 . 6 . 1 . 1 RAERATIVE Di'ACRIPTION O !. tS can be divided into three processes as follows:
i l
[1] Co lection, segregation and pil adjustment (2) Evaporation and distillate ion exchange
[3] Cont a.trates collection and transfer to CSS or WTF l 11 . 6 . 1 . 1 . 1 collection, segregation and pl1 Adjustment i
Liquid waste streams can be collected by one of the following tanks: 35104, 5D15B, er 7D 2. Tank 35104 has a capacity of 22,000 litres while 5D15B has a capacity of 56,950 litres. Tank SD15B serves as the primary feed tank for the evaporator via Pump 71 P 04. Alternatively, as a backup to Tank 5015B, 35104 can feed the evaporator via Pump 71-P 01. Decontaminated supernatant, the stages ol' sludge wash solutions and the melter feed concentrator everheads will be pumped into Tank SD15B and then sent to the evaporator.
Tank 7D 2, in addition to being able to receive process liquids, is also cross tied trith Tank 35104 to handle surge volumes, as mentioned above.
Tank 7D.2 is a primary collection tank for this system.
CAF0778:3RM 37 l
WVNS SAR 005 Rev. 3, Draft D O Liquids can also be collected in Tanks 7D 2 and 13D8 for transfers to the VTF.
A series of valves in the ULD Pump Room has been designated no the distribution manifold. This manifold allows for flexible use of Tank $D15B as follows:
o Tank SD15B contents can be directly pumped to the evaporator via Pump 71 P 04 chrough Elves H 310 and H-309; o $D15B contents can be pumped to Tank $D15A1 via Pump 71 P-04 through Valve H 308; o SD15B contents can be pumped to Tank 7D 2 via 35104; and o 5D15B contents can be pumped to Tank 5D15A1/A2 via Pump 71 P-04 through Valve H-306.
- 11. 6 . 1 . 1 . 2 Evaporation and Distillate lon Fxchange
(
As described in Section H.6.1.1.1, process liquids originate from Tank SD15B and are pumped to the evaporator via pump 71-P-04 through Valves H-310 and H 309 and LCV 100. These liquids are in the range of 500 ppm to approximately 40 w/o dissolved solids depending upon the controlling ionic specien. If the solution is greater than about 40 w/o solids the solution may be diverted to CSS without evaporation for confinement in a cement matrix. Additional restrictions on dissolved solids concentrations are imposed by the CSS Process Control Plan and TR-1RTS-5.
The solutions are fed to the evaporator from Tank SD15B or Tank 35104 at a nominal rate oi 23 litres / min. Steam flow to the evaporator reboiler is controlled by flow control valve FCV-111. A level control system controls the set point of the Feed Flow Controller (LCV-100). The evaporator is equipped with a temperature indicator. A specific gravity controller (DIC-029) controls the removal of concentrates (evaporator bottoms) with a Pump (P-16)
() on a preset specific gravity signal. Evaporator concentrates are cooled to approximately 35 C by a concentrates cooler (71-E-005) before being pumped to CAF0778:3RM 38
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WNS.SAR 005 Rev. 3. Draft D tank $D15A1 or SD15A2 in UPC. The concentrates are then pumped to the CSS waste dispensing vessel, i
Evaporator overheads vapor passes through three (3) reflux inactive bubble cap ..
I trays and then through a high efficiency deentrainer wire mesh to extract liquid mists. An internal water spray is available to wash down the wire mesh i in nase of a high AP across the mesh, i In start up' mode, evaporator condensates flow to the start up side distillate surge tank via Valve 11 154. This distillate is recirculated to the evaporator until the evaporation operation is stabilized. The distillate is then sent to the run side of the distillat surge tank via Valve 11145 from which it is ,
pumped to the zeolite ion exchanger (71 D 003) via Pump 71 P 15. After sainpling, the liquid is routed to the Interceptors and then fed to the existing LLWTF (02 Plant) for further processing and release to the l environment. f Evaporator distillate is puroped frorn the distillate surge tank via Pump P 15 to a zeolite ion exchanger which is solely devoted to evaporator distillato processing. This ion exchanger is equipped with a differential pressure transmitter across the bed and an efflumnt radiation monitor. Instrument readout and alarms are located on the LWTS Control Panel. Off spec effluent i i is diverted to Tank SD15B (>5E 03 pCi/mL gross beta) or the Interceptors (>3E-07 pCi/mL gross beta) via the PPC manifold. -
After extended periods of evaporator operation it may be necessary to perform i
a cleaning operation to remove accumulated solids. The solids increase ,
j radiation background near the evaporator, lower its boiling capacity and ,
i
- accumulate fissile isotopes in the evaporator scale or sludge in the bottom I
head. The solids form because of chemical changes to dissolved salts as they are heated. Since these solids will not dissolve in water alone it is necessary to use up to 2M nitric acid (<12%) to convert them into a soluble form. The analyses in section H 9.8.1 indicate that criticality is not a concern during evaporator cleaning. Ilowever, approximately one gram per liter of boron (as boric acid) inay be added to the nitric acid to act as a neutron poison.for fissile isotopes which raay be present.
CAF0778:3RM 39 i
.,,,.e---,,.m..,-~.m _ _ _ _ . , , , , , . . . - - - , ..-.m , , , , _ , _ - - ~ _ _ _,,-._---.-._m-.,-,---,. . - . , , - , . , - - - . ,
WVN5 SAR 005 Rev. 3, Draft D The cleaning solution is placed in the evaporator and heated until sampling results reflect limited effectiveness of further scale dissolution.
Condensate is returned to the evaporator to maintain a constant liquid level. The spent solution containing the dissolved solids is cooled and transferred to a holding tank for sampling. This solution will not be suitable for cementing in CSS because of high activity and cement recipe qualification requirements; it will be routed back to the high level waste tank (8D 2) af ter pH adjustment. All temporary holding tanks and transfer lines will be flushed and/or sparged.
Airborne concentrations of NOx and nitric acid fumes at the main plant stack release point will be less than 36 ppm and 5 ppb, respectively, over a four hour period (Burn, 1991). These concentrations would be approximately 666 higher if the V0G scrubber and condenser were to become inoperable.
Atmospheric dispersion will further reduce the concentrations (well below the applicable threshold limit values time weightid average) at potential on site and off-site receptor locations. No impact on the integrity of the HEPA filters is expected at such low concentrations of nitric acid fumes.
The neutralized solution will be returned to Tank 8D 2. Therefore, this
)
process will not result in any additional liquid releases to the e nviro nment . The cleaning operation will remove radionuclides held up from other waste streams (mostly decontami.3ated supernatant and sludge washes).
Therefore, no net increase in airborne radionuclide emissions is anticipated from this operation.
Depending on the accumulation of solids, cleanouts may be performed more than once over the life of the system.
l CAF0778:3RM 40
_ _.. . . . . _ . _ . . ____._-__._ __ ..__..m. _ __ . _ _
VVHS SAR 005 !
Rev. 3. Draft D I 11 , 6 . 1 . 1 . 3 Concentrates Collection and __ Transfer l s !
Evaporator concentrates leave the evaporator at approximately 109"C. They are cooled to approximately 35"C in the concentrates cooler and pumped to ;
Tank SD15A1 or SD15A2 for temporary storage. Process control limits for this !
waste stream are as follows:
' ?
o Liquids in the range of 500 ppo to about 40 w/o (depending upon the !
lonic species) are concentrated to a maximum of 46 w/o dissolved solids. Lower limits will be imposed on concentrates to be transferred i
to CSS in order to meet waste form requirements. ;
o A limit of 50 C1/mL Cs 137 is imposed on concentrates generated in ;
LWTS in order to meet shicidin6 requirements. Much lower limits will [
be imposed on concentrates to be transferred to the CSS in order to l t
meet waste form requirements. L
() Concentrates are pumped via Pump 71 P 05 or 71 P-06 through Valves 11301 or 11304 respectively to the CSS Waste Dispensing Vessel in the 01 14 Building I for incorporation in cement.
l l
11 . 6 . 1 . 2 FLOW SilEETS I t
r t
- 11. 6 . 1 . 2 . 1 Pipin t and Instrument Details i Figures H.6.1 1 through H.6.1-17 contain the latest revision of the piping and instrument detail drawings which are applicabic to the Liquid Waste Treatment System,
- 11. 6 . 1 . 3 IDENTIFICATION OF ITEMS IT)R SAFETY CONCERNS The Liquid Waste Treatment System's operational objective is to significantly reduce the volume of liquid waste requiring solidification and disposal.
The LWTS is remotely operated from a control room located in the 01 14 Lullding addition. Shielded valve galleries and pump niches have been l
l CAF0778:3RM 41 l
t
_ 4._ -.___._. _ _ . _ _ _ . _ - _ - . . _- - - _ . . _ _ _ _ . _ _ . _ _ _. _
VVNS SAR 005 Rev. 3, Draft D included in the design to reduce exposure rates in areas where repair or
{
maintenmec ork must be performed. Major equipment replacement or repair can j be supported by complete system flushing to reduce the exposure levels in l areas such as XC3. All routinely occupied areas are designed to maintain area exposure rates less than 0.25 mR/hr. All operations and work require proper [
i radiation and safety precautions as specified on Radiation Vork Permits (RVPs) i and Industrial Work Permits (IVPs),
Piping and the various process components engineered for LVTS rrovide proper ;
containment of radioactive liquids and solids (resins and filter backwash) !
during all phases of system operation. The V0G System will ensure confinernent f i
of airborne radioactive material and hazardous chemicals from process vessels l and tanks throughout the system in the main process building by maintaining !
I various degrees of negative air pressure consistent with the radioactive ;
i airborne concentrations. For all other areas of the main process building, the Main Plant Ventilation System provides differing degrees of negative air pressure, again consistent with potential airborne contamination and, like the ,
V0G System, to ensure that air leak. age is into, rather than out of, f potentially contaminated areas. ;
t P
All effluents fr a the site are monitored to ensure that releases are in ;
compliance with DOE Order 5400,5 (see Section 11.8.2.1) . This program is [
described in Section A.8.6 of Volume I. !
I i
- 11. 6 . 2 PROCF.SS C11EMISTRY AND PIIYSICAL CllEMICAL PRINCIPI.FS !
l I
Vaste stream process chemistry can be maintained within applicable process j requirements for solidification of waste in CSS or return to the VTF by means [
l of the Chemical Feed System. Depending upon waste pil and sample (tank) f volume, positive displacement pumps can add either nitric acid (llNO3 ) or !
sodium hydroxide (Na0ll) as required. Chemical additions can be made to l,
l Tank 7D2, SD15B, SD15Al and SD15A2. Precautions are taken to minimize l processing batches of vaste liquid that contain quantities of organic !
components which can significantly affect efficient system processing during l
[
evaporation, filtration or ion exchange. -
i I
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CAF0778:3RM 42 l
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WNS SAR 005 ,
Rev. 3, Draft D
[
i 11 . 6 . 3 MECllANICAL PROCESS SYSTIMS ;
- 11. 6 . 3 . 1 C01D CllEMICAL RECEIVING, llANDLING AND TRANSFTR Two types of cold chemicals are routinely received, handled, and transferred during system operation. Acid and caustic cheinicals provide a means of pil adjustinent to batches of liquid to he processed by LVTS. The Chernical Feed System is located in the LXA with storage tanks available for acid and !
caustic. Transfer of material to replace depleted stock is made via l hard piped connections to the appropriate storage tank under operator control f and surveillance. f i
f 11 . 6 . 3 . 2 FEED PREPARATION AND llANDI.ING r
Batches of liquid radioactive waste are received into LVTS tankage au ;
described in Section ll.6.1.1. The operation is remotely performed and no I direct handling is required. !
11 . 6 . 4 CllEMICAL PROCESS SYSTFMS +
r I
- 11. 6 . 4 . 1 PROCESS SYSTEMS !
t The Chemical Addition Systern which is used to adjust the pH of batch tanks [
prior to processing. This process is described in Section 11.6.2, ,
?
- 11. 6 . 4 . 2 COMPONIWT/ EQUIPMENT SPldtES Replacement parts are carried in sufficient quantity to replace worn and [
damaged portions of valves and pumps associated with the chemical process f systema. These include spare valve internals and actuators of all major sizes [
of valves installed in t he system. In addition, spare seals and diaphragms j are warehoused to support repair and maintenance of the chemical addition !
pumps. Nu major components are carried in spare since the components are designed and constructed to last the anticipated life of the system t (10 years), f e
i CAF0778:3RM 43 :
\.
Utility Air, Utility Water and Project Electrical Supply ate tha support systems necessary to effectively operate LVTS. These systems are described in Section B.5.0 of Volume 11.
- 11. 6 . 5 . 1 INSTRUNENTATION AND CONTROL SYSTIMS 9
Process instrumenration and centrol systems are designed and specified to provide the primary indications of off standard operating conditions. ,
Instruments used for process control are designed to fail safe. The following list of general specifications was used to insure proper instrumentation and control of LVTS:
o LVTS is designed with sufficient instrumentation and controls such that it can be started, operated, monitored, and shat down from a single, centralir.ed remote control area. A dynamic graphic or CRT display located on the control panel aids in the prevention of operator error, o Remotely operated valves hvve position indicators on the control panel only when the panel is energized.
o System instrumentation provides indications (annunciation), alarms or both under abnormal or undesirable conditions which could increase the potential for unchecked system releases or diminished equipment performance, l
o Process signals, alarms, interlocks automatic process control, specific access, redundancy, and means for calibration (e.g., pressure taps, or procedures for instrument removal) are included in engineering design.
o In cell (XC3) elt:tronic sensing elements are kept to a minimum due to i the environmental conditions. Where possible, level, density and i
pressure measurements are made by hydraulic or pneumatic probes.
CAF0778:3RM 44
WHS.SAR 005 Rev. 3. Draft D o All effluent release points are monitored and sampled in accordance with ANSI N13.1-1969 (R1982).
o Provisions are made to obtain representative samples of liquid radioactive wastes for proper process control, o Instrumentation and control systeros are redundant where appropriato.
Figures 11.6.51 and 11.6.5 2 show the general diagrams of the LVTS Control Panel.
11 . 6 . 5 . 2 SYSTEM AND COMPONENT SPARES Control panel cornponent spares are carried for a nuober of indicators, controllers and recorders in quantities commensurate with their isoportance to the operation of LVTS. Spare cards are also in stock to support centinuous PLC operation. Spare instrurnents and components are carried to the extent recommended by the rannufacturcr to support normal maintenance aad repair.
O 11.6.6 IRTS CONTR01. R0(M Figure }!.6.6 1 shows a general arrangement drawing of the Control Room located in the 01-14 Building addition. CSS and LWTS share this room to control system operations. The control panel layout is included in Section 11.6.5.1.
- 11. 6 . 7 l#TS SANPl.ING_AND ANAI.YTICAl. Rl71UIREMENTS AND PROCFDURES Liquid fed to LVTS from STS for proccasing will be sarnpled from Tank 8D 3 and 5915B. LWTS product (concentrates) will be sampled from Tanks $D15A1 or
$D15A2. These analyses will support materials mass balance and criticality considerations for fissile material being solidified in a cement matrix or j held up in the evaporator (TR IRTS-11).
All sample lines can be flushed with utility or dominera11 zed water as
!. necessary to ensure valid sample results. Detailed sarnpling requirements for
. LVTS are listed in the STS/INTS/ CSS Sampling Plan and LWTS procedures.
CAP 0778:3RM 45
. . - - . - . . _ _ - . - . - - . - - _ - . . - - - . . . - . - - _ _.. - . . ~ - - . - . .
i WNS. S AR. 005 l Rev. 3, Draft D !
l REFFRFRCES IUR SECTION 11.6.0 i American National Standards Institute (ANSI) N13.1 196v (R1982), Specification and Perfortnance of On. Site Instrumentation for Continuously Monitcring
{
Radioactivity In Effluents. I Burn, P., 1991, Memo E0:91:0055 to C. C. Baker, "NYSDEC Stack Release Permit j l
Modification for LWTS Evaporator Cleaning," dated April 26, 1991. ;
Saha, A. K. ,1986 Document WNS PN 003 to Distribution, "LVTS Process Control !
t Interlocks," Rev. O, dated March 19, 1986. i WDP,1985, Safety Analysis Report, Volume II, Existing Plant and Operations. !
i I
WDP , 1985a , Safety Analysis Report, Volume IV. Cement Solidification System. f i
f WDP,1985b, Safety Analyris Report, Volume III. Vitrification System.
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