ML20079F368
| ML20079F368 | |
| Person / Time | |
|---|---|
| Site: | West Valley Demonstration Project |
| Issue date: | 09/27/1991 |
| From: | Dooley D, Faillace E WEST VALLEY NUCLEAR SERVICES CO., INC. |
| To: | |
| References | |
| REF-PROJ-M-32 WVNS-SAR-005-01, WVNS-SAR-005-01-R03, WVNS-SAR-5-1, WVNS-SAR-5-1-R3, NUDOCS 9110080133 | |
| Download: ML20079F368 (213) | |
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Records Managernent
, Ext. 443', MS 52 HP:91:1159 a September 27, 1991
- a Controlled Distribution of VVNS SAR 005, SAR Volutte IV Liquid Waste Treatitent System, Revision 3 Distribution ec: HF Letter Log, MS 52 Original, MS-MRC Attached is VVNS SAR 005, SAR Volume IV Liquid Waste Treatitent Sy s t e rn ,
Revision 3, which has been assigned to you under controlled distribution. Replace your current copy with the att.sched in your manual. Copies made from a controlled document are to be markod t!NCONTROI.LF.D befora distribution. To acknowledge receipt of this doeurtent, sign, date, and return the _ attached controlled distribution receipt acknowledgement to the undersigned by October 11, 1991. ('v} For your convenierce, a startped (of f site recipients only) return address has been placed on the reverse side of the controlled distribution roccipt acknowledgement; fold, staple, and place in the mail. . QC kA Y.! E. Lindbe'fgtt;--Rfcords Processon) Records Management West Valley Nuclear Services Co., Inc. BEL Approved:
- C. M. Schif fhaut rf Supervisor
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I O VEST VAIJJ:Y Dl: MONS OtAT10N l'RtLIECT f:AFFTY ANALYSIS REl' ORT V0111ME IV l' ART 11 1.lQUID WASTE TREATMENT SYSTEM REV. 3 Controlled Copy No, , o care,, _ 1
" " "* " " v " 3 - o ^ " - 5 g West Valley -
Revision Number 3 Demonstrat. ion Proj. ect Revision Date 09/27/91 ~ Eng. Release #1435 Per ECN #4257 Per ECN #4353 SAFETY ANALYSIS REPORT FOR LIQUID WASTE TREATMENT SYSTEM D. A. Dooley and E. R._ Faillace Safet y and Environmental Assessment July 1991 REQUIREMENT FOR ENVIRONMENTAL REVIEW MET BY REFERENCED DOCUMENT: WVDP-049 DATED December 1985 APPROVED HAZ ARD CLASSIFICATION: Low DATE OF APPROV AL: April 8, 1988 REFERENCED DOCUMENTS WD:85:0372 WD 35:0293 DW o8:0174 APPROV ALS : b[f 1 n {b_ _ f_ 627 4( jCogni zant Manager, Date 0 k&A Staf f ManageP7Date h / f ( l v -f N} $ Chairman, WVNS Radiatio f and Safety Conyttee, Date
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West Valley tiuclear Services Co., Inc. P.O. Box 191 h cAF0778:3RM
\W 1816, Rov.1 West Valley, fly 14171-0191 DOE Approved DW:91:0682 Dated August 26, 1991
WNS SAR 005 Rev. 3 RECORD OF REVISION TROCEDURE If there are changes to the procedure, the revision taut.ber 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. Exatupl e : The vertical line in the marc.in indicates a change. l Revision On Rev. No. Description ut changes Page(r' Dated
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0 Original Issue All 1 Engineering Release #1435 08/26/88 2 Per ECN #4257. Rev. 2 was approved but not issued for controlled distribution. All changes for Rev. 2 are indicated ir. Rev. 3. 3 Per ECN #4353 09/27/91 s 1 W-1807 A, Rev. O i CAF0778:3RM
{ ! 1 VVHS.SAR 005 1 Rev. 3 l 1 . 5 > j RECORD OF REVISION (CONTINUATION SilEET) j j Rev No. Description of Changes Revision)on-Page(s Dated j
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WVHS.SAR 005 Rev. 3 j VEST VAIJ.EY DIMONSTRATION PROJECT I SArt.TY ANAL.YSIS REI' ORT V01EME IV LIQUID WASTE TREATMENT SYSTEM TABII 0F CONTENTS Section Page LIST OF TABLIS . . . . . . ....... .......................................... xi LI S T O F F I GUR E S . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .......... xil LIST OF ACh'.ONYMS AND ABBREVIATIONS........... ............ ........... xv
- 11. 1 . 0 INTRODUCTION AND GFNERAL DESCHII' TION OF Tile FACil.1TY. ..... 1 H.1.1 Introduction....... ................ ........ ............. 1 11 . 1 . 2 General Plant Description.. .... .. . .................. . 2 11 . 1 , 3 Ceneral Process Description................................ 3 D s/
s 11 . 1 . 4 Identification ot' Agents and Contractors................... 4 H.1.5 Structure of this SAR...... ....... ..... ................. 5
- 11. 2 . 0
SUMMARY
SAFETY ANALYS I S . . . . . . . . . . . . . . . . . . . . . . .. .......... 7 11 . 2 . 1 Site Analysis......................... .................... 7 11 . 2 . 1 . 1 Natural Phenomena.......................................... 7 11 . 2 . 1 . 2 Site Characteristica Affecting the Safety Analysis. . . . . . . . 7 11 . 2 . 1 . 3 . Effect of Nearby Industrial Transportation, and Mil i ta ry Fac ili t ie s . . . . . . . . . . . . . . . . . . . . . . . , . . ............. 8 11 . 2 . 2 Radiological Impact of Normal Operations...... ............ 8 11 . 2 . 3 Radiological Impact from Abnormal Operationa.. ..... ..... 9 II.2.4 Accidents .................................. .............. 9 [) V CAF0778:3RM - lii -
UVNS SAR-005 llev. 3 ! TAhly. OF CONTENTS (CONTINU__ED). - Section Page 11 . 2 . 5 Conclusions....... .. .. . . . ... .. .... .... .. .. 10 References for Section 51.2.0. ........... . ........ .... 11 11 . 3 . 0 SITE CllARACTTERISTICF. . . . .... ... . .. ......... ......... 12 ll 3.1 CEOCRAPHY AND DEMOGRAPlIY OF VVDP ENVIRONS . . .......... ... 12 11 . 3 . 2 NEARBY INDUSTRI AL, TRANSPORTATION AND HILITARY FACILITIES. , 12 H.3.3 METEOROLOGY............ ... ... . ....... ....... ....... 12 11 . 3 . 4 SURFAC HYDR 01DGY......... .. . . . .... .......... 12 11 . 3 . 5 SUBSURFACE HYDR 01ACY...... . . ..... .. ........ 12 H.3.6 CE01AGY AND SEISM 01AGY. . . . .. ... ... . . . .. ....... 13 11 . 3 . 7 SITE ECoiACY.... .... .... . . ...... . . . ...... . 13
- 11. 4 . 0 PRINCIPAL DESIGN CRITERIA. . .... . . .,. .. .... .. 14 11 . 4 . 1 Purpose of the Liquid Waste Treetment System (1.*tTS)........ 14 H 4.1.1 LWTS Functions......... .. .. . . .. . ...... ... . ...... 14 H.4.1.2 Prime feeds to the LVTS, . . , , . ... ... .............. 14 H.4.1.3 LVTS 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 Genera 1......................... ..... ... ................ 16 H.4.3.2 Protection by Multiple Confinement Barricts and Systems.... 16 11 . 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 Vaste Handling and Storage... .... ........... 18 1
CAF0778: 3PJi ' iv -
l WNS - SAR-005 i Rev. 3 i piit.E OF CONTEq_SJCONTINUEIQ Section Pago
- 11. 4 . 3 . 8 Industrial and Chemical Safety... ... . . . 18 11 . 4 . 4 Classification of Stnictures. Components, and Systerns. ... 19 11 . 4 . 5 Decontatnination and Decormnissioning. ..... . .. . .. .. 19 11 . 4 . 5 . 1 1MTS Construction. .. . .. . . ... . . ... .. .. .. 20 keterences for Section 11.4.0. .... . . . . . 21 11 . 5 . 0 IVrS FACILITIES DESIGN, ......... ...... . . .... 25 H.5.1 Smrunary Description of the INTS. .. . . . , .. 25
- 11. 5 . 1 . 1 Location and Facility Layout. . . . . .. . 25 11 . 5 . 1 . 2 Principal Features.... . . ... . . . . .. .. ... 75 11 . 5 . 2 LWTS Facilities... ... . .. . . . . . . . . 25 11 . 5 . 2 . 1 Structural Specifications. . .. . ... .... 25 11 . 5 . 2 . 1 . 1 Process Building Modifications.. .. . . .. .. . .. 27 11 . 5 . 2 . 2 LVTS layout.... ...... . . . .. . ..... ,. .. 27 H.5.2.2.1 Radioactive Operations.. .. ....... . . . ..... 27 11 . 5 . 2 . 2 . 2 Nonradioactive Operations. . . . .... . . . .. ..... 28 H.5.3 LWTS Support Systems.... . . .... ... . ..... ....... 28 11.54 3.1 Development of Support Requirements for LWTS. ... .... .. 28
- 11. 5 . 3 . 1 . 1 Cell Ventilation. . . . .. . .. ... .. 28 11 . 5 . 3 . 1 . 2 f.mergency Power Requiremnnts. . ... . . .. . . . ...... 29 H.5.3.1.3 Honitoring System (s). . ..... . ..... . ... ....... 29 11 . 5 . 4 Service and Utility Systern Descriptions. . ..... .. . ...... 30 H.5.4.1 Process Building lleating and Vent ilation System. . . ..... .. 30 i H,5.4.2 Electrical........ ...... .... . ..... . . . ...... 30 11 . 5 . 4 . 3 Compressed Air......... .. . . . .. . . . ... 30 11 . 5 . 4 . 4 Steam Supply and Distribution. . . . .. . . .. . . 31 CAF0778 : 3101 -v-
WNS Salt 005 Ray. 3 TABLE OF CONTENTS (CONTINUEDI 8ecti.SB l'atel l s l 11 . 5 . 4 . 5 Water Supply....... ........ .................... ......... 31 ) I ll . 5 . 4 . 6 Sewage Treatroont. . .. ..................................... 32 ,
- 11. 5. 4. / Safety Communications and Alarins. . ....................... 32 11 . 5 . 4 . 8 Fire and Explosion Protection System.... .................. 32 11 . 5 . 4 . 9 Maintenance Systemn........... ... .. ... ...... .. ...... 33 11 . 5 . 4 . 1 0 Cold Chemical Systems.... . . ........ ......... .. ...... 34 References for Section H,5.0. ..... ... ..... .......... 35
- 11. 6 . 0 IMTS PROCESS SYSTEXS., .... .. ... ... ......... .......... 37 11 . 6 . 1 Process Description.... ... .. . .... ... ............... 37 '
H.6.1.1 Narrative Description.... .... ... .. ................ 37 11 . 6 . 1 . 1 . 1 Collec tion, Segregation and pil Adj us troent . . . . . . . . . . . . . . . . . . 37
/^ 11 . 6 . 1 . 1 . 2 Evaporation and Distillate Ion Exchange.................... 38
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11 . 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 11 . 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 11 . 6 . 3 . 1 Cold Chemical Receiving, llandling and Transfer... ........ 43 ! H 6.3.2 feed Preparation and llandling. . . . . . . . . . . .......,,..... .. 43 H.6.4 Chemical Process Systems.,. .................. ............ 43 H.6.4.1 Process Systems.. ......... .. ......... . ........ ...... 43 11 . 6 . 4 . 2 Component / Equipment Spares,............... ................ 43 H.6.5 Process Support Systems............. .......... .,........ 44 m H.6.5.1 Instrumentation and Control Systems.... .... .. . .... .... 44 I CAF0778:3RM v1 - 1 _ - -- . ___ _ . _ _ _ _ _ _ _ __ _ . ~ . _ . _ _ --
WVNS.SAR 005 R2v. 3 Tall 12 0F CONTENTS (CONTINUEDJ , O Page-t i Section 11 . 6 5 . 2 System and Component Spares..... .... . . . . . . . . . . . . ..... 45 l ll . 6. 6 LWTS Control Room............... .. . . . . . . . . . . . . . . ..... 45 : l i H.6.7 LVTS Sampling and Analytical Requirements and Procedures... 45 l References for Section H.6,0....... ..................... 46 11, 7 . 0 VASTE CONFINIMENT AND MANACIMENT. ............. . . 47 H.7.1 Waste Management Criteria..... .......... . . . . . . . . ..... 47 l 11 . 7 . 2 Radiological Vastes... .. . . ....... . . . . . . . . ..... 48 11 . 7 . 3 Nonradiological Wastes. . . .. .. .. . . . . . . . . . ..... 48 H.7,4 Off-Gas Treatment and Ventilation.. . . . . . . . . . ..... 48 11 . 7 . 4 . 1 Operating Characteristics. . .. . . . . . . . . . . . . . . . . ., .. 48 11 . 7 . 4 . 2 Safety Criteria and Assurance. .... . . . . . . . . . ..... 49 11 . 7 . 5 Liquid Waste Treatment and Retention. . . . . . . .. . 49
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11 . 7 . 6 Liquid Waste Solidification... . . . . . . . . . . ..... 49 11 . 7 . 7 Solid Wastes......... ... ............ . . . . . . . . . . . ..... 50 References i< r Section 11. 7,0. . . . . ....... . . . . . . . . . . ..... 51
- 11. 8 . 0 RADIATION PROTECTION.... ...... .. ........................ 52 H.8.1 Ar.suring that Occupational Radiation Exposures Are As Low As Reasonably Achievable ( AIARA) . . . , . . . . . . . . . .,... 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 11 . 8 . 2 . 2 Airborne Radioactive Haterial Sources....... . . . . . ..... 56 l [3
\ w/ t H.8.3 Radiation Protection Design Features..... . . . . . . . . . ... . 57 l CAF0778:3RM - vii -
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WNS SAR-005 Rav. 3 TABLE 01.* CONTlWrS_{ CONTINUED 1 r ! Section Pat,e i (u H 8.3.1 LVTS Design Features. ...... ... ........... ... ... ...... 58 11 . 8 . 3 . 2 Shielding,. . . . . ..... .... . .. , ...... ........ ........ 58 H,8.3,3 Ventilation.............. ............... ........... ..... 59 l H.8.3.4 Area Radiation and Airborne Radioactivity Monitortrg Instrumentation............. . ......... ...... ... ...... 60 H.8.3.5 Equipment and Process Decontamination Factors. ..... .... 60 H.8.4 Projected On+ Site Dose Asseanment............... . ........ 61 11 . 8 . 5 Health Physics Program for LVTS.......... ....... ... ..... 62 11.8.6 Off Site Dose Assessment.. .. . . . .. . .. . . ... .. 62 l l 11 . 8 . 6 . 1 Effluent Monitoring Programs..... ... .......... . ...., 63 i H.8.6.2 Analysis of Multipl. Contribution.... . . ......... 63
- 11. 8 - 6 . 3 . Projected Doses From Airborne Releases..... ... ... ....... 63 1
( H.8.6.4 Projected Doses From Liquid Releases. . . ... .... .. ...... 65 (v Re ferences for Sec tion 11. 8.0. . . . ............ .. ........ 67 i 11 . 9 . 0 IATTS ACCIDIXT SAFETY ANALYSIS................. ... . ... 76 H.9.1 Abnormal Operations.......... . . . .... ......... ....... 76 11 . 9 . 2 Abnormal Events Prime Inputs to LWTS 6 Evaporator System 76 H.9.2.1 Failure of Tank 5D15B...................................... 76 11 . 9 . 2 . 2 Evaporator Feed Pump (71-P 04) Fails.................. ... 76 l I l H.9.2.3 Loss of Evaporatot Steam Supply.... ... .......... ........ 76 l li . 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 Coo 1er............................ 78 l H.9.3.2 Evaporator Burps Its Contents (Eructation)................. 78 l l CAF0778 : 3PJi - vill - 1 l
VVNS-SAR DOS Res. 3 TABl.E OF CONTENTS (CONTINUED}
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( Sectton Page 11 . 9 . 3 . 3 Overflow of Process Tanks and Equipment to Vessel off 0as................. . . , ,. . ...... 78 H 9.3.4 Loss of Instrument Air / Utility Air....... .. .... .... . 79 11 . 9 . 4 Abnormal Events Off.Cas Treatment................ ....... 79 H.9,5 Abnormal Eveats Ventilation System..... . . .. ........ 79 H.9.6 Accidents.......... ... .... .. .. .......... . . ..... 80 H,9.6.1 Accidents Analyzed......................................... 80 11 . 9 . 6 . 2 Source Terma............... . . .... .. . . . ..... . ... 80 H.9.6.3 Off Site Radiation Doses.... . ... ... . .. . . ..... .. 81
- 11. 9 . 6 . 4 Rupture of Process Line Between the Process Building and 01 14 Building.. ............. ... . ....., 82 H.9.6.5 Rupture of the LVTS Pipe Chase and/or the Pipe Chase Leaving the 01 14 Building. . ...... ..... .. 82
/ H 9.6.6 Process Tank Rupture outside XC3.... .... .... . ......... d3 s
H.9.6.7 Tank Rupture Inside XC3..................... .............. 84 H.9.6.8 V0G HEPA Filter Failure..... ..,....... ..... ........ ... 64 H.9.6.9 VDG 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 Cleanin6 Solution............... ................... ...... 88 H.9.7 Minor Accidents.......... .. ............................ 89 H 9,8 Potential for Nuclsar Criticality.... ..... ............... -89 H. 9.8.1 Evaporator Acid Wash....... .... ...... ................... 90 References for Sect'on H.9,0,............................., .92 11 . 1 0 . 0 CONDUCT OF LWTS OPERATIONS.. . . ,,... ............. .... 112 es H.10.1 Organizational Structure. .. . .. . ..... ... ..... ..... 112
%J CAF0778:3RM ix -
WVNS-SAR-DOS Rev. 3 l TABl.E OF CONTENTS (CONCIDDF.D1 Section Pam
- 11. *.0. 2 Preoperational Testing and Operation.. .. .. . . .. . 112
- 11. 1 0 . 2 . 1 Administrative Procedures for Conducting the Test Program., 112 11 . 1 0 . 2 . 2 Test Program Description. . ..... . .. ........ .... 112 11 . 1 0 . 2 . 2 . 1 l'hysical Facilities............. ... . . . ....... 113 11 . 1 0 . 2 . 2 . 2 Process Operatioits, . .. . .... . . .... ... . ... . 113 11 . 1 0 . 2 . 3 Test Discussion .. ...... . . . .. ... . ...... 114 11 . 1 0 . 3 Training Programs... .. ....... . . . ........ .. ..... 114 11 . 1 0 . 3 . 1 Scope, objectives, and coals of the LWTS operator Qualification Program. . . . . ... .... . .... 114 11 . 1 0 . 3 . 2 Operation Prerequisites..... . . ..... .. . .. ...... 115 11 , 1 0 . 3 . 3 Training Resources. . ..... .. .. . . .. .... 116 11 . 1 0 . 3 . 4 Training Content Outline. .... . ... . ......... . .. 117 11 . 1 0 . 3 . 5 Qualification Verification / Documentation. . . . . .. . .. 118 11 . 1 0 . 3 . 5 . 1 Examinations. ..... .. . . ... ..... . . .... . ...... 118 11 , 1 0 . 3 . 5 . 2 Documentation........ . .......... . ........ .... . 119 H.10.3.5.3 Quality Assurance... . . ...... ............. ...... ... 119 11 . 1 0 . 3 . 6 Requalification. .. .. .. . . . . .. . . . . ........ . 119 H.10.4 Normal LWTS Operations. . . .. . .. ..... . ............ .. 121 H.10.4.1 LWTS Procedures........ .. .... . . .. .. . . . ... ... 121 References for Section 11.10.0. .. ....., . ... .... .. . 122
- 11. 1 1 . 0 OPERATIONAL SAFETY REQUIREMFKl'S. . .. .. .. . ,,..,... ... 123 11 . 1 2 . 0 QUAI.lTY ASSURANCE.. ... . ..... ........ .... .. .......... 124 11 . 1 2 . 1 Quality Assurance Program.... .... . .. . ...... .. 124 H.12.2 Implementation.. ..... .. . .. . .. .. ... . , ....... 124 References for Section 11.12.0. . .. . . . ... . .. 127 CAF0778:3RM x-
_- . . . . . ~ - . . . . . . - - ~ - - - . - - . . - . - . . WVN.S.SAR 005 Rev. 3 VotDME IV ( LIST OF TABI.F.S Number Titlo Pag H.1.5-1 Current (1990) Structure of the Vust Valley Demonstration Project Safety Analysis Report............. ............. 6 L.4.1 1 Radionuclide Ittventory (1991) of , Decontaminated First Sludge Wash ....... .. ..... ..... 22 ' H.4.1+2 Projected Activity in Waste S t r e ams t o b e P ro c e s s e d by LVTS . . . . . . . . . . . . . . . . . . . . . . . . . . 21 H.4.4 1 Safety and Service Classification of Important Structures, Components, and Systems Associated with the Liquid Waste Traatment Sys tern. . . . . .. ... .......... 24 n.5.3 1 LVTS Utility Requirements..................... .......... 36 ; H.8.2-1 LVTS Waste Stream Feed.................. ............... 68 11 . 8 . 2 2 Projected Radionuclide Inventory in Tank 80 2 Decontaminated Sludge Washes (1991) Processed by LVTS.... 69 (s s H.8.3 1 Resul ts of LWTS Shielding Analysis . . . . . . . . . . . . .......... 70 H.8.3-2 Equipmcr o and Procesa Decontamination Factors.... ....... 71 H.8.6-1 Projected Plant Stack Discharge From Waste Streams to be Processed by LVTS...................... ........... 12 H.8.6 2 Collective and Maximum Individual Doses Predicted l From Stack Releases Resulting, From Routine Operation L of tWTS.................................................. 73 l H.S.6 3 Comparison of Maximum Airborne Concentrations of Selected Nuclides at Site Boundary With Current l DOE Derived Concentration Guides (DCG)................... 74 H.8.6 4 Collective and Maximum Individual Doses Predicted From Liquid Pathway Releesco Frorn Processing Sludge ! Wa s h e s Th rou gh LWTS . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . , 75 I H 9.1 1 Potential Abnormal Events for LWTS Subsys tems or Maj or Process Component s . . . . . . . . . . . . . . . . . . . 94 H.9.1 2 LWTS Tank Volumes and Secondary Containment........ ..... 103
<- H.9.6 1 Dose to the Maximally Exposed Off Site Individual (w) for the Significant Radionuclides from the Evaporation of Evaporator Concentrates Associated with Rupture of Process Line... .... ........... ....... ............ 104 CAF0778:3RM xi -
WNS SAR 005 llew. 3 j V0WMK IV
- 143T _0F _ TABl[.S _
(CONCWLED)
?!t.mbo r , tit 1o Pano, H.9.6 2 Dor.e to the lisxirts11y Exposed Off Site Individual for Significant Radionuclides froni the Evaporation of Deconte.minated Supernatant Associated with Rupture o2 Process 1.ine in tbv New iNTS ftpe Chase (170' el)..... 105 11 . 9 . 6 - 3 Dose to the Maximally Exposed off Site Individual for the Sir,nificant Radionuclides: from the Evaporstlua of Evaporator concentrates (50 pct /mi. Os+137) for a Tank Rupturc outside XC3... ..... ...... . .. . . . .... 106 H.9.6 4 Dose to the Maximally Exposed Off Site Individual for the Si& nificant Radionuclides from the Evaporation of Liquid from Spent Zeolite Resin to the Floor of XC3.. ... 107 H.9.6 5 Done 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 Maxitaally Exposed Off-Site Individuni for tht3 Significent Radionuclidea fot .a HEPA Filter Fire Accident.. . ......... .... .. ......... .. ...... 109 H.9.6 7 Dose to the Maximally Exposed ofC Site Individual for the Significant Radionuclides Evaporated from a Spill of Evaporator Cleaning Solution Fo11 wing Rupture of Trann fo r Pipe. . . . . . . . ...... ....... 110 H.9,8-1 Maximum Concentrations of Fissile Material in INTS Evaporator Concentrates. , .................... ........ 111 11.12.1 1 Quality 1.evels of Important 3tructures.
Components, and Syr.tems Associated with the Liquid Waste Treatment System. ..... ........ ..... ..... . .. 128 CAF0778:3RM xii -
UVNS SAR-005 Rev. 3 V011tMf; IV
. LIST OF FIGURES 11.1.3 1 Prituary LVTS Process Flovpath i
11,4.1 1 Process Diagrain LVTS - 901D-02051. Rev. 1
- 11. 4 . 1 2 Process Otagtarn LWTil 901D 020S2, Rev. 0 11 . 4 . 1 - 3 Procesa Diagrarn - ISTS 901D-020S3, Rev. O H.4.1-4 Process Otagram lyts 901D 020S'. Rev. 0 ft.$.1-1 VVDP Site Plan 900E 1988, Rev. 0 11 ', . 1 2 Rey Plan Process Building (P,echtel 151t M-1. Rev. 3) 11 . 5 . 2 1 Coueral Arrangement LWTS Plan El .100,00' - 901D-041, Rnv. 2 11 . 5 . 2 - 2 Ceneral Arrange: cent INTS Plan El .116.50' - 901.0 042, Rev. O R.S.2-3 General Arrangeinant LUTS Plan El.131.00' - 901D 043, Rev. 2 H.S.2 4 General Arrcngement 1.VTS Plan El. 144.00' - 901D-044, Rev. 0 11.5.1 5 General.Arrangenent INTS Plan El. 160.00' - 60iD-043, Rev. O
!!.5.2 6 General Arrangement INTS Sectians 9010 046 Rev. 1 11.5.2 7 Ceneral Arrangement INTS Sections 901D+047, rev. 0 11 . 6 . 1 1 P&ID LWTS -
901D 021S1. Rev. 10 H.6.1 2 P61D LWTS - 901D 021S?, Rev. 4 , H 6.1-3 P&lD LV15 - 901D 021S3, Rev. 2 = 11 . 6 . 1 4 P61D t#IS - 901D 021S4, Rev. 0 11 . 6 . 1 - 5 P61D INTS - 901D 021R$ Rev. O
- 11. 6 . 1 6 P&ID LWTS - 901D 02106, Rev. I 11 , 6 . 1 7 P&lD LVTS - 901D 021S7, Rev. O H.6,1-8 P61D LVTS - 901D 022, Rev. 14 ,
H.6.1 9 P61D LUTS - 9010 023S1, Rev. 9 11 . 6 . 1 - 1 0 P61D LWTS - 901D 023S2, hev. 9 H.6.1-11 P61D LWTS - 9010 023S3, Rev. 3 CA10778:3RM xiii -
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WNS-SAH-005 l Ray. 3 i Y9.fE E IV
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%# LIST OF FJCURF.S (CONClllDF.D)
H.6.1412 f*&lD LVTS - 901D 024. Rev. 1$ H.6.1 13 P61D LVTS - 90lv 026 Rev. 9
- l. 6.1 14 P&lD LVTS - 9010 049, Rev. 9 H.6.1 15 P6!D INTS - 901D 050, Rev. 5 H.6,1.16 P&ID $NTS -
90lb 051. Rev. 4 H 6.1 17 P&In Lvis - 901D 059. Rev. 10 H.6.5 1 INTS control Panel outline Drawing - 901D 395, Rev. 1 H.6.5 2 LWTS Control Panel - Front View Layout - 901D+396 Rev. 11
- 11. 6 , 6 1 : 7tS Control Room Caineral Arr.sngement - 9000-1180, Rev. 4 O
( i l l [. l I: 1 'O , v CAF0778:3RM xiv -
. . _ .. _ . - _.- _ _ _ _._ _ _ . . _ . . . - _- . _ _ _._ _ _ . _ _ _ ._ ._ _ _ . _ = _ . - - _ . _ __
l WVNS-SAR-005 Rev. 3 i VollME IV LIST OF ACRONYMS __AND ABhMEVIATIONS A1 ARA As Low As Reasonably Achievabia C Canti, Profix for 10"2 D C Degrees Celsius CAA Cell Acwess Aisle CAM Continuous Air Monicor CEDE Committed Effective Done Equivelent CRT Cathode Ray Tube CSS Cement Solinif t :ation Systern D50 Decontaminat .on and Decornmissioning 8 DCC Derived Concentration Guides DOE Department of Energy DOP Dioctylphthalate , LOT D*partment of Transportation AP feetta Pressure (pressure drop) EPA ,..vir emer.tal Protection Agency
#e CV Flow Control Valve
- CCR Ceneral Purposa Cell Crane Room l
COA General Purpose Cell Operating Aisle HFPA High Efficiency Particulate Air Nitric Acid Lh IITP High Total Dissolved Solids II" _ Heating / Ventilation
' I'4P Industrial Work Permit kW Kilowatt LCV Level control Valve LLVTF Low Level Waste Treatnent Pscility (02 plant)
LTDS Low Total Dissolved Solids
- IJ4A Lower Wata Equipment Aisle -
l LWC Liquid Waste Cell LWTS Liquid Waste Trcatment Syrten LXA Lower Extraction Aisin y Micro, Prefh for 10 4 l m Meter m Milli, I'retix for 10'3 MCC Motor Control Center
.\
CAF0778:3RN - xv -
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WHS.SAR 005 Rev. 3 V01DMP, IV LIST OF, ACRONYMS AND__ ABBREVI ATIONji (CONCIDDED) NaOH Sodiun liydroxide NFG Nuclear Regulatory Commission 0/1 On the Job Training oJ Operational Safety Requirement P6tt Piping and Insttunent Diagram < PCR Process Chamical Room Pt.C Prograttanble 1.ngic Centroller PPC Product Purification Cell psi Founds Per Square Inch psig Pou.3ds Per Squate Inch Cauge ppm Parts Per Million RVP Radiation Work Permit SAR Safety Analysis Report SPDE5 State Pollutant Discharge E11mluation Syster. (New ' fork State Permit) STS Supernatant Treatment Sys tora TDS Total Dissolved Solids ULD Uranim Londout UPC Uranium Troduct Cell UVA Upper Warm Aisle UXA Upper Extraction Aisle VOC Vessel Off Gas VF Vitrification Facility Weight Percent w/ o WDP West Valley Derr.onstration Project WNS West Valley Nuclear Services Company Incorporated XCR Extraction Chemical Room XC3 Extraction Cn11 3
' SA X Extraction Sample Aisle O
CAF0778:3RM - xvi -
VVNS SAR 00$ Rev. 3 O H.1.0 1,NTRODUc*r10N AND CENERAL DESCRIPTION OF 111E FAC11.ITY H.1.1 JNTRODUCTION i This Safety Analysis Report (SAR), WVNS SAR 00$, Volume IV, Part H. Liquid Waste Treatment System (LVTS), was prepared to meet the requirements of the
.U.S. Department of Energy (DOE) Order DOE $481.1B (U.S. DOE, 1986), Idaho Operations Office (ID) Order ID 5481.1A (U.S. DOE ID, 1989), and West Valley Nucicar Services Co., Inc. (VVNS) Policy and Procedure WV 906, Rev 8 (VVNS, ,
1990). Further introductory information relating to the VVDP Act, ancillary tasks and supporting activities that must be accomplished may be obtained from Section A.1.1 of Volume 1 of the Project SAR (WVNS SAR-001). Former PUREX_ reprocessing activitiew generated high level radioactive waste (HLV) that is stored in Tank 8D 2. This HLW is separated into an alkaline supernatant and sludge. It is the task of the WVDP to convert ths HLV into borosil'.cate glass for ultimate storage in a federal repository. (The Os preliminary SAR for the Vitrification Facility (VF), in which the HLW will be i converted into borosilicate glass, is WVNS SAR 003). In order to accomplish
. t this mission pretreatment of the HLV is necessary, r
The pretreatment is performed.by the Sludge Mobilization and Wash System ' (SMVS), analyzed in WVNS SAR 004, Volume III, Part D, and the Integrated Radwaste Treatment System (IRTS) which consists of the.STS, also analyzed.in VVNS SAR-004; the Liquid Waste Treatment System (LVTS), described and analyzed in this SAR; the Cement Solidification System-(CSS) described and analyzed in VVNS-SAR-008, Volume IV, Part G; and the Drum Cell (DC), described and analyzed in VVNS SAR 007, Volume IV, Part K. l The LWTS;was operated-f rom 1988 through 1990 to process the decontaminated t supernatant produced by STS (see Revision 1 of this SAR). This' revision of l. the LVTS SAR is an update to focus on the next HLW processing step. l: o O CAF0778:3RM 1
- - - - - _ - - _ - - - - . _ _ _ = . ~ . ~ . , - , .- . . - . _ - . . -,, , a , _ . , - - - , , .- -
VVNS SAR.005 Rev. 3 The SMVS will remove the interstitial salta and salt crystals from the Pt' REX V sludge. This will be accomplished ir. four cycles by mobilizing the aludge with the sludge mobilization pumps and using dilute caustic solution to suppress actinide solubility while dissolving the salt and salt crystals. The wash solution will then be treated by lon exchange in Tank 8D 1 to remove most of the cesiwn, strontium and plutonium. The washed sludge will be stored in Tank BD 2 until it is used as ac1ter feed to the VP. The LVTS will then procens the decontaminated sludge wash solutionn by evaporation. The LVTS product consists of a concentrated solution that will be sent to CSS for incorporation in a cement matrix. As part of this process, the LVTS will produce airbortw and liquid ef fluents in a f orm suitable for discharge to the environment. In the future, LVTS will also be used to process radioactive 11gulds in support of the vitrification facility and in final plant decontamination.
- 11. 1 . 2 CENERAl. PIANT DESCRil'I'ipj U
The VVDP site is located in a rural setting approximately 50 km (30 mi) south of Buffalo, New York, at an average elevation of 400 m (1,300 ft) on New York State's western plateau. The plant facilities used by the VVDP occupy approxim tely 63 hectores (156 acres) of chain-link fenced area within a 1,35P hectares (3,300 acres) reservation that constitutes the Western New York Nuclear Service Center (VNYNSC). The communities of West Valley, Riceville, Ashford Hollow 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 VNYNSC. The major LVTS process components are located in cells insido the main process building of the former nuclear fuel reprocessing facility (Figure H.5.1-1 and 11 . 5 . 1 2 ) . The liquid feed tank, SD 15B, and the concentrate collection tanks,
$D-15A1/A2, are located in the Uranium Product cell (UPC). The major
,e s components of the system, the evaporator and distillate ion exchange columns, CAF0778:3RM 2 1
i ud
_ _ . _ . _ . . . ~ . _ _ _ _ _ _ _ _ _ . _ . _ _ _ _ . . _ _ . _ . _ _ _ . . . _ ._ t VVHS.SAR.005 ; 1 Rev, 3 e i are located in the Extraction Cell 3 (XC3), LVTS interfaces with STS/SWH3 by I receiving liquids from Tank 8D*3. LVTS product is sent to CSS through the i j' - Vaste Dispensing Vessel (VDV). The LVTS control room is shared with CSS and 1 is located in the 01 14 building, , a 1 i There are several important design considerations to ensure the safety of the . 4 system. These are described in detail in Section 11.8.1.2. The most important ) are that the process vessels and cells are maintained under negative pressure, i that structural barriers have been designed such that the confinement of ; !. liquid radioactive vaste vill not be compromised by any credible design basis { event, and that redundancy in critical aspects of the operation is used. An l example of the redundant nature of the operation is the ventilation systems. , 4 Both of the ventilation systems used by the LVTS contains redundant i
- ventilation trains and are connected to emergency backup power. '
Additional design considera .ons can be found in Section 104.0. Operational considerations are maintained by administrative and procedural control as ! described in Section H.8.1.3. Also, Operatior.a1 Safety Requirements (OSRs) ' a ! - and Technical Requirements (TRs) are presented in Volume VI, Part M.11 of the Project SAR.
- 11.1,3 CENERAL PROCESS DESCRIPTION
- 1
- A simplified-description of the overall VVDP activities is. presented in 1 Section A.1.3 of Volume I and includes those processes required for }{LV *
, handlin6 and vitrification. The-LVTS process presented in this volume will . provide the means to concentrate liquida such that a cemented waste form can be produced in the CSS facility. j .I l-i j - Figure 11.1,31 illustrates the primary process flowpath for LVTS liquida, The , LVTS process is-fully automated and is controlled from the LVTS control 9 . room. Decontaminated sludge wash solution is transferred from Tank 8D-3 (the-SHVS product tank) to Tank SD 15B .(the 15,000 gallon LVTS feed tank) by means
- of pump P 01. Pump P 4 transfers the liquid from Tank 50 15B to the'high
) efficiency ovaporator/reboiler 31017, which in run in thermosyphon mode. The ( ' CAP 0778:3RM 3 ; i
.l -
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_ . . _ _ _ . . -. . _ _ . _ .. . _ _ .. _ _ . _ _ _ . - .. - _ _ _ _. ~ , _ _ . _ _ _ _ VVNS SAll.005 Rev. 3 distillate from the condenner la processed through a realite ion exchange column to remove cesium and strontiurn. This liquid effluent is then sent to the low level liquid waste treatment facility (LLWTF) for addit'.onal treatment prior to discharge to the envirotwent. Caseous effluents trom the evaporation i process are collected by the Vessel Off Cas (V0G) system, llEPA filtered, and discharged through the main plant stack. The concentrates produced in the evaporator are pulled through a concentrates cooler E 00$ by pump p-16 and fed to Tank ;D-15A1 or SD 15A2. The concentrater are then transferred to the CSS Waste Dispensing Vessel. Instrumentation pinced at n. ategic points j throughout the sistein allow the proccas pararteters to be monitored from the 1.WT5 control room in real time. Fced and product tanks, as well as effluent , points can be sampled to ens.ure that the liquid waste stream is within the process parameters. The LW'1S was designed to allow sufficient flexibility so that if one flow path were teirporarily down for maintenance, the process could he re routed alon6 an alternate path. The LVTS van originally designed to include a low dicsolved solids liquid treatment subsystem to provide tecycle water for other 1RTS procesr.es. The procen and invtruaentation diagramw in this SAR illustrate the low TDS and recycle water subsystems. Most of the equiprent was installed but is not currently operational. The impacts of operating this equipment will be analyzed in'a revision to this SAR if, and when, this equipment hecomes operational, 11.1.4 IDENTJJ;ICAT,T_ON OF ACPKrS AND CONTRACTORS Section A.1.4 of Voluac 1 identifies the agents and contractors responsible for luplementing the VVDP. The relationships between VVNS and agents and contractors is illustrated in Figure A.1.4 1 of Volume 1. I - l CAF0778:3RM 4 t l-
+
WNS SAR.005 ' Rev. 3 4 11 , 1 . 5 spilCTtfRE OF Tills SAM L The concept of this modular SAR is explained in Section A.l.5 of Volume I. , i The structure of the SAR is patterned af ter NRC Regulatory Guide 'J.26. See the Table of Contents, which reflects this pattern. Since it was published as Table A.1.51 of Volume 1 in June, 1985, the format of the WDP SAR has evolved as required by changes in Project allostones. As originally conceived, sludge mobilization, washing and transfer of all HLW (loaded neolite 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.l.5 1). The current plan is to issue a separate module, Part E of Volume III, to cover the HLW transfer operations. A copy of : the current structure of the Project SAR is provided in Table H.1.5-1 and will be added t.o Volume I during the scheduled routitw update. Scructural changes in response to revisions in Project milestones are anticipated. O l' p O
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VVNS.SAR 005 Rev. .1
'IABLE 11.1.5 1 0 _ CURRENT _GH0j STRUCTUREJF TllE VEST VALLEY DEMONSTRATION PROJECT SAFETY ANAINSIS f(EPORT
{ VVNS SAR Volume Titic Part Desi mation 1 Project Overvi% and Ceneral Information A 001 11 Existing Plant and Operations B 002 Ill tilgh Level Waste Vitrification 3 o Vitrification Fac111ty l C Ti(D o Supernatat.t Treatment System 2 D 004 o SMS and llLV Transfer E TBD IV Waste Management, Storage and Disposal o !!1gh* Level Vat.te Interim Storage F TBD o Ceteent Solidification System G 008 o Liquid Waste Treatment System 11 005 O o Size Reduction Facility 1 010 o Lag Storage Facility J 009 o Disposal Area Operations K 00(s & 007 V Final Decontamination, Decommissionini, L TBD and Uaste Shipment VI Operational Safety Requirements M NA Notes: 1, SARs for the Vitrification Facility (Part C) and liigh-i.evel Waste Interim Storage (Part F) to be combined into one document.
- 2. Includes a revision for the Sludge Mobilization and Vash System
- 3. Preliminary SAR for the Vitrification Facility is SAR 003 CAF0778:3RM 6
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Qg' \um AN (D-QNEF3NG gg4c,gg op4w,Ng FIGURE H.1.3-1
VVHS SAR 005 Rev. 3
- 11. 2 . 0 ypMMARY SAFETY ANALYSIS
\('\
x_/ This Safety Analysis Report (SAR) was prepared to address safety issues associated with the operation of the Liquid Waste Treatment System (LWTS). The purpose of LWTS is to process radioactive liquid waste, to reduce liquid waste volume, and to provide feeds to Lhe Cement Solidification System (CSS) , or Octurn concentrates to the High Level Waste Tank Farm (WTF). This module of 8.he Project SAR is limited to the construction and operation of LWTS. LWTS ! 1 intarfaces to CSS, the VF, and the Supernatant Treatment System (STS) are also l l discussed. l The LWTS ginally described in this report included a recycle water subsys teia ; however, as of May 1991 this subsystem had not been installed, and there are no current plans for installation, rhis safety analysis encompasses operation of the LWTS without the recycle option. l The following seccions summarize the radiological impacts of LWTS g'"] operations, No on nite or off-site releases of hazardous ehemicals in excess
\/ of TLVs are anticipated under normal operations or accident conditions, 11 . 2 . 1 SITE ANALYSIS 11 . 2 . 1 . 1 NAIURAL PIIENOMENA See Section A.2.1,1 of Volume I.
11 . 2 . 1 . 2 SITE CllARACTERISTICS AFFECTINC Tile SAFETY ANALYSIS The maj rity of components of the LVTS associated with the processing of radioactive wastes are located in Ext action Cell 3 (XC3). Other components are located in the Urar'ium Product Celi (UPC), Uranium Loadout (ULO) area, and the Product Purification Cell (PPC) r.s well as throughout the site (e.g., interceptors, in ground tanks, etc.). Accidents are analyzed in Section H.9.6 for process equipment and other components which support LWTS operation. The (T~ release of radioactivity from these acciuents could be direct or indirect. A CAF0778:3RM 7
VVNS-SAR 005 Rev. 3 direct reletse may involve a spill or a leak outside the confines of the LVTS piping or ventilation system which results in area contamir.at 'on, release of airborne activity or evaporation of liquids to the atmospler An indirect release occurs when all material from a = pill can be containu. by structures and ventilation with subsequent release from established discharge points. The Process Building is part of the Main Plant and is at an elevation well ) above flood potential. Natural phenomena (earthquake, tornadoes, high winds, and snow loading) are accounted for in accidents where these conditions may have an impact. Seismic phenomena in particular may be initiating events for some of che accidents analyzed '.n Section H.9.6. 11 . 2 . 1 . 3 EFFECT OF NEARBY INDUSTRIAL TRANSPORTATION, AND MTLITARY FACILITIES See Section A.2.1.3 of Volume 1.
- 11. 2 . 2 RADIOIDGICAL IMPACE OF NORMAL OPERATIONS Both on site and off-site dose assessments were performed in order to detennine 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 arnual collective occupational dose was estimated to be 16.5 person-rem (Section H 8.4), 6.5 for operations and 10 person rem for maintenance activities I. 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 H.8.6.3 and H.8.6.4). AIRDOS-EPA (an atmospheric dispersion code) was used to estimate the atmospheric transport and diffusion of radioactive particulates. Site specific metecrological 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
WNS SAR-005 Rev. 3 O O 11. 2 . 3 RADIOIIXHCAL IMPACT MtON A11 NORMAL OPERATIONS Abnormal operations are events which could occur from malfunctions of systems, operating conditions, or operator error. Abnormal events are only of consequence for those avstems in the IRTS which process, control, or confine radioactivity. The abnorwal events considered (Section 11,9.2 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 ACCIDFNTS 1 Se,ren 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 (V0G) System and the Main Plant
,r g Ventilation System, and a spill of evaporator cleaning solution following a b 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 process line ruptures are 42 and 0.45 mrem, respectively. The maximally e posed on-site individual is estimated to receive doses of 10 and 8.1 mrem, respectively, from those ground level releases. The di'; ketween the two accidents concerns the type of material being hand! od .aantity of material released. For the tank rupture outside XC3 (5D15Ai in UPC), the dose is calculated as 4.1 E-03 mrem. Aaalysis of a tank rupture accident inside XC3 -(Spent Zeolite Tank, 71-D-007) leads to a predicted dose of 4.8 E-07 mrom
- to the maximally exposed off-site individual The dose to the maximally i
exposed off-site individual for the VOC System HEPA failure is 0.34 mrem while
- i. the HEPA fire dose is projected to be an order of magnitude higher at 3.4 mrem. The dose for a failure of or fire in the Main Plant Ventilation llEPAs is considered to be the same as or less than iat for the V0G HEPAs. The dose I
from a spill of evaporator cleaning solution following the rupture of a 1 transfer pipe is calculated as 120 mrem to the maximally exposed off-site V individual and 2.2 rem to the maximally exposed on-site Individual. CAF0778:3RM 9 l
WVNS-SAR 005 Rev. 3
) Due to the batch mode of IRTS operations, accidents in the ST3 will not affect LVTS (other than delay operations), Similarly, accidents originating in LWTS will not have a direct impact on CSS and Drum Cell operations, 11 . 2 . 5 CONCLUSIONS This Safety Analysis Report was prepared to meet the requirements of DOE Order 5481,lB and DOE-ID Order 5481.1A, " Safety Analysis and Review System" (USDOE, 1986a, and USDOE, 1989) and WVNS Policy and Procedure WV-905, " 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,
" Contractor Industrial Hygiene Program" (USDOE, 1985). The analysis demonstrates that the facility can be operated safely. The facility has been designed to minimize radiological hazards to members of the public and project staff by reducing the amount of waste in the process at any one time comeensurate with process requirements and by conducting operations remotely within a sealed, shielded cell. The analyses contained herein predict no doses of consequence to either on-site or off site individuals as a result of normal operations or accidents. Conservative assumptions lead to an estimated collective dose to workers of 16.5 person-rem / year for normal operations.
Calculated doses to the maximally exposed off-site individual were determined for both normal and accident conditions. All doses under normal operating - conditions are within the requirements of DOE Order 5400.5 (USDOE, 1990). All accidents analyzed are enveloped by the criteria for a low hazard facility in DOE ID Order 5481.lA (USDOE, 1989). O CAF0778:3RM 10
. ~ . .
UVNS SAR-005 Rev. 3
, REFERF*NCES }T)R SECTION 11.2.0 l
US DOE, 1989, DOE ID Order 5481.1A, " Safety Analysis and Review System," dated April 11, 1989. US DOE, 1990, DOE order 5400.5, " Radiation Protection of the Public and the Environment," dated June 5,1990. US DOE, 1985, DOE Order 5480,10, " Contractor Industrial b gienc 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 9 1 i O CAF0778:3RM 11
WNS SAR 005 Rev. 3
- 11. 3 . 0 SITE CllARACTERISTICS Site characteristics potentially affecting the WDP as a whole are detailed in Volurne 1, Section A. 3. Site characteristics affecting the LWTS are described
- below,
- 11. 3 . 1 CFDCRAP11Y AND DEMOCRAPIIY OF WDP. ENVIRONS 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 INDUSTRI AL, TRANSPORTATION AND MILITARY FACILITIES See Section A.3.2 of Volume I for a general site discussion. There is no effect on LWTS operations as a result of these site characteristics.
- 11. 3 . 3 METEOF 1DGY See Section A.3.3 of Volume I for a general discussion of meteorology around the WDP. Meterological site characteristics did not affect the LWTS design,
- 11. 3 . 4 SURFACE IlYDROIDGY See Section A.3.4 of Volume I for a general discussion of surface hydrology around the WDP. Surface hydrology characteristics did not affect the LWTS design.
11 . 3 . 5 SUllSURFACE 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 LWTS design. CAF0778:3RM 12
I VVNS SAR 005 Rev. 3
- 11. 3 , 6 CJE0lIX;Y AND SEISMOIIX;Y 1 - w)
, See Section A.3.6 of Volume I for a general site discussion. Site seistnic criterf.a vere ueed in both the original design of the process building as well as structural modifications of the process building to incorporate the LVTS. 4 11 . 3 . 7 SITE EcuIIX:Y I See Section A,3.7 of Volume 1 for a general discussic.n. There is no effect on the LVTS operation as a result of site ecology. 4 i _v 1 1 4 4 ,I
.O lU CAF07/8:3RM 13
VVNS-SAR 005 Rev. 3 O 11. 4 . 0 PRINCIPAL DESICN CRITERIA
.V 11 . 4 . 1 ITRPOSE OF Tite LIQUID WANTE 'IRENIVENT SYSTEM (IVTS)
The main purpose of the LWTS is to process low level liquid radioactive vaste generated as a result of various WVDP activities for eventual solidifcation in cement. Activities expected to provide the largest amount of liquid to be processed include decontamination of 8D 2 supernatant, sludge washing, operation of the vitrification molter feed concentrator, and various plant decontamination ' e ffor ts . LWTS will concentrate liquid wastes into a minimum volume consistent with process requirements, principally by evaporation and ion exchange, and transfer evaporator concentrates to CSS for solidification in cement. 11 . 4 . 1 . 1 IVTS FUNCTIONS The LWTS performs the following functions:
/~S
( i
\- # o Reduces the volume of liquid radioactive wastes received consistent with process requirements.
o Provides a means to coordinate movement and storage of liquid wastes between WVDP processing syster.a. 11 . 4 . 1 . 2 PRIME FEEDS TO Tile IVrS Until the end of 1990 decontaminated supernatant from the STS was the primary feed to the LWTS via Tank SD15B. Four BD-2 sludge washes will be the next
' feed to LWTS (Table H.4.1-1). Two other important feeds to LWTS are the overheads from the melter feed concentrator and d1 contamination wastes. Any feed m:Lerial requiring pH adjustment prior to evaporation or other treatment will be adjusted with acid or caustic solutions as necessary. Table H.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
(~ approximately 50% of the activity requiring disposal (see DOE /EA-0295) . CAF0778:3RM 14
WNS SAR-005 Rev. 3 Figures H,4.1 1 through 11.4.1-4 contain the process flow diagrams for LVTS operation. Detailed information oa vaste streams expected to be processed by LWTS are contained in Saha (1986).
- 11. 4 . 1 . 3 IWrS PRODUCTS AND BY-PRODUCTS If products of LVTS operation are considered to be those materials which are either sent to the WTF, CSS, or to aurface discharge, the LWTS will then produce two identifiable products from its operation. These products are:
- 1) evaporator concentrates (to CSS or WTF), 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 ar 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 floor crains o Spent evaporator cleaning solutions 11 . 4 . 2 STRUCTURAL AND_ MECllANICAL SAF1mf CRITERI A FOR Tile LVrs, The majority of LWTS components are installed in existing structures such as XC3, PPC, ULO, and UPC. 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 WDP, 1985a). Those documents contain the safety criteria applied in the design of the LWTS. Minor modifications of structural me.terials necessary to accommodate LWTS piping and equipment in the Process Building are not considered significant enough to change the overall CAF0778:3RM 15 i
WVNS SAR-005 Rev. 3 structural safety in the above mentioned analysis. Furthermore, the hazards O ansectated with a loss of structural integrity are minor when UWTS is compared 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 LUTS. Seismic analysis of the trench was not considered necessary due to the relatively small quantity of activity present se any one time, or the short time required to transfer evaporator acid wash n etion (Sections H.9.6.5 and H.9.6.11). 11 . 4 . 3 SAIY1Y PROTECTION SYSTEMS
- 11. 4 . 3 . 1 CENERA1.
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 various types of safety protection systems considered necessary for the operation of LWTS appear below,
- 11. 4 . 3 . 2 FROTECTION BY MULTIPLE CONFINEMENT IMRRURS AND SYSTEMS The primary confinement barrier for the relatively low concentration of racioactive 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 LVTS, UPC and XC3 are equipped with stainless steel liners and susps. Sump levels are checked once per shift. The operability of the sump high level alanns is check quarterly. In addition, the transfer pipe trench is designed to drain into a sump. O ! CAF0778:3RM 16
VVNS SAR.005 Rev. 3 All confinement and containment barriers have been designed to limit potential
\- releases of cadioactive material in accordance with generally acc epted As Low As Reasonably Achievable (ALARA) practices in compliance with the latest revision of VVDP 010. " Radiological Controls Manual."
H.4.3.3 PROTECTION BY EQUIPMMT AND INSTRUMMI Si:LECTION P acurement of equipment and int centation for operation of the LWTS was
- done in coupliance with WVNS '
- narance program which is described in Section 12 of Volume I (WVD1 9 .ality levels of the individual systems and components for LW1. able H .12.1 - 1. Current requirements for new equipment 's existing equipment are given in Section H.12.0.
Existing equipment and instrumentation placed in service was subjected to inspection and testing commensurate with its intended use. Process instrumentation was designed to provide the primary indication of
\m/ off. standard operating conditions. This instrumentation provides an indication and alarm under abnormal operating conditions.
H.4.3.4 NUCLEAR CRITICALITY SAF1'rY A nuclear criticality _is not considered a credible event for the types of processes associated with LWTS operation (see Section H.9,8). Therefore, criteria which address nuclear criticality safety have sat been included in
- the original system design.
l. H.4.3.5 - RADIOIDCICAL PROTECTION Construction'and maintenance activities are performed in accordance with VVDP-010. " Radiological Controls Manual." Shield walls, confinement and containment structures as well as administrative controls (procedures, training, Operational Safety Requirements (OSRs], etc.) are used as necessary g 's to maintain radiation doses to occupationally exposed personnel ALARA. CAF0778:3RM 17
WVNS SAR 005
- Rev. 3 4
vs Protective clothing (anti-C's, respiratory protection) is worn when required x-- by radiological conditions. In addition, precautions such as system decontamination and flushing are required in the ecse of necessary contact maintenance. H.4.3.6 FIRE AND EKMDSION PROTECTInN The LWTS has fire detection equipment, alarm systems, and ruppression systems commensurate with potential fire hazards associated with LWTS operation as determined by the WVNS Radiation and Safety group. Fire and explosion hazards are evaluated in accordance with the WVNS Industrial Hygiene and Safety Manual (WVDP 011) and TR-CP-16. These are discussed in Section 11.5.4.8.
- 11. 4 . 3 . 7 RADIOACTIVE WASTE IIANDLING AND STORACE LWTS operations use a number of existing tanks to temporarily store LWTS feed material and process material in different stages of the operation. Storage e- of these liquid materials in any one process vessel or tank is considered to g}
\~l be a temporary condition. Bounding consequences of failures and ruptures of various LWTS tanks are considered in Sections H.9.2.1, H.9.6.6 and H.9.6.7.
< H.4.3.8 INDUS11tIAL AND CllEMICAL SADHT
-The WVNS-Industrial Hygiene and Safety Manual, WVDP-Oll, provides the administrative guidelines and control over industrial and chemical safety in regard to the operation of LWTS. While currently not in use, the LWTS process provides for addition of acid or caustic to feed solutions. Analysis of 9 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 spilled is considered in section H.9.6.11, 1 (
- \s /
CAF0778:3RM 18
WVNS SAR 005 Rev. 3 l (t 11 . 4 . 4 CIASSIFICATION OF STRUCTURES, COMPONENTSuAND SYSTFMS Safety and service classifications of important structures, components, and systems associated with the LWTS are presented in Table 11.4,4-1. The proceduree and criteria used to arrive at the designated classifications are contained in Section A 4.4 of Volume I. 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 (HV) supports, vessel off-gas piping, and ventilation instrumentation ar.d alarms are cla,sified as Safety Class C. The ilV supports and VOC piping are Class C because they ensure confinement of r dioactivity. The instrumentation and alarms for ventilation systems are considered Class C because their los: of function could allow unmonitored releases. Likewise, airborne particulate and area radiation monitors are Class C due to the potential for unmonitored releases should failure occur. O
\w / Sump piping, instrumentation, ar.d alarms are Class C for reasons of confinement of radioactive material and because loss of instrumentation end alarms could lead to undetectsd leakage and potential for inadvertent exposure (see also Section 11.4. 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 radioactive material call for stainless steel (types 304, 304L, 316, 316L).
This wilt allow periodic flushing of tho' system with strong decontamination agents, thus removing the maximum amount of deposited radioactive material. As a result, pctsonnel dose will be minimized during the decommissioning effort. It must be recognized that the LWTS system would most likely be the. last of the WVDP systems to be dismantled due to the key role it plays in waste water management. CAF0778:3RM 19
I WNS + S AR-005 l Rev. 3 f- Decontamination and deconnissioning of LWS will probably take place in a k 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 LWTS D&D. Hazards associated with this type of work are addressed in Volurne II. 11 . 4 , 5 . 1 IFTS CONSTRUCTIUR A Safety Analysis has been written to support the Phase I construction effort , i of INTS (Ploetz, 1986a). It concludes that the initial phase of wor't is , covered by the existing Safety Analysis for decontamination and deconnissioning contained in Volume II. ! To support all future phases of LVTS construction a Hazard Classification and I 1 an Environmental checklist were prepared (Ploetz, 1986b, 1986c). In i accordance with the criteria of WNS Policy and Procedure W-906 and DOE ID Order $481.1, LWTS construction meets the criteria of a low hazard activity. The Environmental Checklist demonstrates that engineering controls will p maintain proper ventilation for all construction activities. Liquid and solid l d waste generated by LVTS construction will be properly handled, stored and 1- disposed, l All LWTS construction activity was performed using approved procedures and in accordance with WDP-010 Radiological Controls Manual" and WDP Oll
" Industrial Hygiene and Safety Manual."
l l l l l l l
%J CAF0778:3RM 20 l
l l .
WVNS SAR 005 Rev, 3 l I REFERFI!CKS R)R SECTION 11.4.0 Letter WD:86:0804, Rykken, L. E., to W. W. Bixby, " Referenced Radionuclide Content of High Level Vaste," dated November 10, 1986. Memo 1111:86:0056, A. K. Saha to Distribution, "RTS Waste Stream Data Sheets, Rev 4," dated March 27, 1986. Nuclear Fuel Services, 1962, Final Safety Analysis Report, Volurnes I through IV, Revision 0 through L. Ploctz, D. K., 1986a, Letter 1111:86:0057, D. K. Ploet z to J . L. Knabenschuh,
" Revised Safety Analysin for Construction of INTS - Phase I."
Ploetz, D. K., 1986b, Letter AD:86:0027, Technical Director to J. L. Knabenschuh, " Revised llazard Classification for Construction of LVTS." Ploetz, D. K., 1966c, Letter 1111: 86 : 0049 , D . K . 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 Vaste, West Valley Demonstration Project, Part I: Environmental Assessment, April 1986, ( CAF0778:3RM 21
WVNS-SAR-005 Rev. 3
<~N TABLE 11.4.1-1 RADIONUCLIDE INV}yrORY (1991) OF DEcoff!'AMINATFD FIRST St.UTX;E VASil(1)
Radionuclide bS"SOEf[ikk" __
^bbhhsI(?)
H3 1.26 E-05 2.51 E+01 C-14 2.22 E-05 4.43 E+01 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 E+02 Sr 90 1.13 E 04 2.26 E+02 Y-90 1.13 E 04 2.26 E+02 Tc 99 2.56 E 04 5,13 E+02 , Ru-106 1.40 E-07 2.81 E-01
- Sb-125 3.62 E 05 7.24 E+01 Te-125m 8.12 E-06 1,62 E+01 1-129 3.40 E-08 6.80 E 02 Cs-134 4.09 E-07 8.18 E 01 Cs-137 8.19 E-04 1,64 E+03 Ba 137m 7.75 E-04 1.55 E+03 tN Pm-147 1.18 E-05 2.36 E401
\s ,/ 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 U-235 1.26 E-08 2.51 E 02 U-238 1.18 E-07 2.36 E-Oi Pu-238 3.10 E-05 6.20 E+01 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 Am 241 5.17 E-06 1.03 E+01 Am 243 3.69 E-07 7.39 E-01 Cm 244 1.48 E 06 2.95 E+00 TOTALS 2.66 E-03 5.31 E+03 (1) Derived from Tabal D.8.2-2 of STS SAR assuming DF - 8 for Pu, DF - 5 for Sr, DF - 1000 for Cs, and 1:1 dilution with water. (2) Based on 2 E+06 liters. ['s CAF0778:3RM 22-
l WVNS-SAR 005 Rev. 3 TAB 12 11,4.1 - 2 III PROJECTED ACTIVITY 1h WASTE STREAMS 'It) BE PROCP.SSED BY IMTS Activity War.te Stream .(Curies)_ 8D 2 Decontaminated Supernatant Processed from 1988 tc 1990 First Sludge Wash 5.31 E+03 Second Sludge Wash 1.60 E+03 Third Sludge Wash 4,19 E+02 Fourth Sludge Wash 1.09 E+02 Decon of Plant Cells 6,4 E+02 Melter Feed Concentrator Overheads (2) TBD Spent 2eolite Slurry 7,76 E+00 Filter Backwash 2.43 E402 TOTAL 8.33 E+03 zh (1) Sludge wash activities derived from Table D-8.,2-2 of the STS SAR, all others derived from Waste Strea? Data Sheets, Saha (1986) and Rykken (1986), e (2) This stream will be returned to the Waste Tank Farm for eventual encapsulation in glass and is not included in the column total. l 1 CAF0778:3RM 23
l WVMS SAR 005 I Rev. 3 TABI.E 11. 4 . 4 - 1 SAFEIT AND SDIVICE C1.M SIFICATION OF IMlWITANT Sll10CTURES, COMPONFKi3, AND SYSTEMS ASSOCIATED WITil Tile LIQUID WASTE TREATMENT SYSTCt SAFETY SERVICE COMPONENT OR SYSTEM CIASS CLASS STRUCTURES Existing Process Building (Modified) N III Shield walls (New) N III Maintenance access doars and hatcher. N III Air Iock doors N IV Stainless steel liner N IV Sumps and associated drainage linec N IV Tloor drains and lines N IV Pipe supports N III Conduit supports N IV Heating / Ventilation supports C III Pump vault N III Valva pit U III
' WASTE FROCESSING Collection tanks and associated piping N IV Evaporacor, condensur, and coolers N III Filter N III Ion Exchangern N III C.J Liquid food tanks Concentrate tanks N
N 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 MONITORINC SYSTEMS Process instrumentation and controls N IV Ventilation instrumentation and alarms C Ill Sump instrumentation and alarms C III Airborne particulate monitors C III Area radiation moni tors C IIT O CAP 0778:3BM 24
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e ng g ha* LOW LEVEL LIQUID M51E SYSTEM E- V i i '?". *.:., !.TL m WC j! F " ' * " * * ' W3 i ; , M i i i f _4__._ 7'S,.f;ll'7'% 6 ,i ! 4 + w my_1
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- 11. $ 0 IMTS FACILITIES DESIGN
- 11. 5 . 1
SUMMARY
DESCRIPTION OF T11E iMTS 11 . 5 . 1 . 1 IDCATION AND FACILITY LAYOUT The majority of LVT* process equipa.ont is located in XC3 of the Process Buildtng. Figure 11.5.1 1 shows the layout of the WDP f acilities, with the M Process Building located in the approximate center of the former NFS c otaplex . Figure 11.5.1-2, 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 existing tanks located throughout the facility are used to support liquid transfer and temporary storage for LWIS operation. They are identified by the word " existing" and by dashed lines in the-process flow diagrams in Section 11. 6,0, ( 11 . 5 . 1 . 2 PRINCIPAL FEATURES u Principal festures of the site are contained in Section B.S.I.2 (Volume 11). I Main Plant Systems provide utilities such as electrical power, compressed air, steam and water (see Section 11.5.4) The high total dissolved solids system along with the high efficiency waste evaporator are located in XC3. All system controls are h ated in a control room outside the 01-14 Building at the 100' elevation.
- 11. 5 . 2 IRIS FACTI.ITIES 11 . 5 . 2 . 1 STRUCTURAL. SPECIFICATIONS Structural requirements fur LMTS meet the pressures and temperatures as specified in the process flow diagrams, Figure ll.4.1-1 through 11.4,1-4. All process components meet the structural requirements of ANSI A58.1, while the l CAF0778:3RM 25
-& <L4_-A& -rA4- A M a> rdh-M &3-] wTMi- b u u 4m_m- A- :h14L , d Ae>-mL4,-
WVNS SAR 005 Rev. 3. { I. . - structural aspects of the process building are covered under the New York State Building Code. Material requirements for LWTS equipment is listed in VVNS.(1986) and will not be repsated in this document. The existing main process building and modifications made to incorporate the l l IJiTS have been designed and built to UBC Zone II seismic criteria. The results of seismic' analyses are summarized in Section B 5.2.1.1 of Volume II' [ of the VVDP SAR.
-l Exteriors of components inste*1ed indoors but not inside cells are capable of enduring _the following ambient design conditions for at least ten years:
o Pressure O 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 0C o Wind Load 155 kilometers por hour o Snow Load 176 kg/m 2 l- o 'Raiu 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
=0 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 CAF0778:3RM 26 ,
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a . - - _ - _ _ - _ - - _ . _ _ _ . .. -- VVNS SAR 005 , Rev. 3
- 11. 5 . 2 . 1 . 1 Process _ Building Modifications n.on completion of decontamination and decommissioning efforts in XC3, minor modifications were made to the cell to support placement of LWTS process equipment. Numerous wall 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 area compared to the XC3 environment. Other minor modifications were made in PPC for valve gallery support, installation of rumps and equipment in ULO and UWA, installation of the ion exchange hopper ano filter backwash skid in the Extraction Chemical Room (XCR), as well as modifications made to LXA, the Lower Warm Equipment Aisle (LVA), Upper Extraction Aisle (UXA) and Process Chemical Rooin (PCR).
- 11. $ . 2. 2 IMTS 1AYO',
The iral layout of LWTS components, associated piping and systems are shown on tl weral arrangement drawings, Figures H. 5. 2 1 through Figures 11.5. 2 7. 11 . 5 . 2 . 2 . 1 Radioactive Oparations The majority of LVTS radioactive operations are confined to XC3 where the bulk of the process equipment is located. However, many other locations such aa PPC, ULO, 1PC and steas of the site which contain storage er transfer tankage can also be conuidered a part of radio 9etive operction. All areas within the main process 1 building where LWTS process components exist are maintained under slightly negative pressure by either the V0G System or Main Plant Vcntilation (see Section H.S.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 LVIS evaporator can act upt radioactive feed from Tank 35104 using Pump 71-P 01, or Tank SD15B using Pump 71-P-04. Concent rates from the evaporator exit the Process Building and flow to the 01 14 Building, feeding the CSS Waste Dispensing Vessel. All waste ,trean.s from the zeolite columns either return to CAF0778:3RM 27 l
VVNS SAR 005 Rev. 3 , l I
- LVTS for further processing or are routed to the LLViT (0?. Plant) for discharge l
.tia the La,oon system. Helter feed concentrator everheads will be returned to the VTF after concentration by LVTS. l 11 . 5 . 2 . 2 . 2 Nonrannonctivo Operationa Two areas exist where LVTS 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 cotoponents. The second is the Chernical Feed System located in LXA. Nitric acid (HNO )3 and modima hydroxide (Na0ll) storage tanks with separate positiver displacernent pumps and 1sociated equipment are the inajor cornponents of this systern. These areas are serviced by Main Plant Ventilation and inaintained under slightly Ogative pressure. The LVTS Control Room can also be considered as part of nonradioactivo operations,
- 11. 5 . 3 1RTS SUPPORT SYSTFMS, Table 11.5.31 presents an overview of utility service required for INTS
\ operation. 11 . 5 . 3 . 1 DEVE1DIMPRT OF SUPPORT RFI)UIRIMFWTS FOR INTS
- 11. 5 . 3 . 1 . 1 Cell Vent 11; tion The Main Ventilation System is the primary source of ventilation for XC3 and other areas which contain INTS process equipreent within the Process Building. The Main Ventilation System description and operational characteristics are contained in Volume II, Section B.S.4.1 of the Vest Valley Demonstration Project (WDP) SAR.
(% Q CAF0778:2RM 28
WNS SAR 005 Rev. 3 11 . 5 . 3 . 1 . 2 fjmergency power Requirementa LVTS Process Systems are not scpplied with auxi)iary power. The system is designed to fail safe upon loss of electrical power.
- 11. $ 3.1. 3 Monitoring SystemJn}
LVTS is a well instrumented process system. Remots sensing capability is required due to the radiation exposure rates and the degree of containination associated with most of the LWTS coinpor.cnts and equipment. Under normal conditions, all LWTS pump motors and valves, with tne exception of block valves at cell walls and maintenance drain valves, can be operated remotely from the LVTS control panel. Process tanks contain level instrumentation with indications (annunciations) and alarrns at appropriate levels. Some process tanks also contain stream density instrumentation. Other parts of the LVTS are outfitted with sensors for flow, temperature, radiation and pressure at appropriato locations for proper process control. 5 Monitoring systems important to safety are listed in Table 11.9.1 1. These include: o Tank high a..d 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 Evapot4 tor high density alarm o Level, pressure, radioactivity, and flow indicators on tanha 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 O V CAF0778 : 3PJI 29 t
WVNS.SAR 005 Rev. 3 11 . 5 . 4 SDtVICE AND _UTil.1TY SYSTEM DESCRil'TIONS 11 . 5 . 4 . 1 PROCESS IkU11blNG lirATING AND VENTILATION SYSTD( Process Building IIV needs are provided by the plant Main Ventilation System (Section B.5.4, Volume II). Briefly, those areas having thn lowest concentrations of airborne activity (e.g., the control room, stairways, 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 nisles and sample alales are maintained at approximately 0.075 kPa VC. This air is exhausted through a filter train consisting of a prefilter and absolute filter prior to exhaust out the main stack. Areas w'. ore contamination is least expected are maintained as contamination +1ree as possiblo by the increasin6 negative pressure requirements engineered into the main plant ventilation system, t
- 11. 5 . 4 . 2 ELECTRICAL, Primary, secondary and emergency power are described in Section B 5.4.2.1 of Voltune II of the SAR. LVTS is supplied with a normal 45 kW of power with 460 velt 3 phase or 120 volt single phase capability. Peak power demand is rated at 75 kW.
- 11. 5 . 4 . 3 COMPRESSED AIR Host 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:
CAF0778:3RH 30 t r , , . - . . _ . _.__._-...,p, , , _ . , . ..,.,m_-- ,, - - , . . . - _ .,
WVHS.SAR 005 Lev. 3 Utility Air Pressure (kPa) Temperature (OC) Litres / Min V(3 Peak 689 320 0 (max) 2800* Normal 689 32 C (max) 560* Instrument Air 334 and 138 32*C (.34 0C 1160 Deu Point) i
- Rated flow at 27 0C, 489 kPa 1
1 LVTS is desi6ned to fail safe in the event of loss of compressed air supply, i The fail safe position of valves (i.e., either open or closed) is indicated on the Piping and Instrument Diagrams (P61Ds). 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.
,m 11. 5 . 4 . 4 STFAM SUPPLY AND DISTRIBUTION Steam supply for LWTS originates from the Plant Steam Supply System discussed in Section B,5.4.4 of Volume II. Saturated steam is supplied at high (1034 kPa) or low (172 kPa) pressure. The major purpose of the steam supply is to provide the heat source for the hi6 h efficiency waste evaporator. In addition, a number of steam eductors located throughout the system are required for operation,
- 11. 5 . 4 . 5 WAT5R SUPPLY l- Section B.5,4,5 of Volume II 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. Domineralized water is also supplied as flush water to the new l (;) CAP 0778:3Rx 31 i l
WNS.SAR 005 Rev. 3 Chemical Feed System and to the Ion Exchange Fill System. Under normal conditions cooling water is supplied at 946 litres /rnin, and desninoralised water at 20 litres / minute. Under peak conditions cooling water is supplied at 1200 litres / min and demineralized water at 150 litres /minuto. Possible consequences of losing cooling water supuly are discussed in Section 11.9.0. 11.5.4.6 SEWACE TRFXIMENT Facilities are available for use in the Main Process Building by LWTS ' Operations Personnel. II.S.4.7 SAETY COMMUNICATIONS AND ALARMS The LWTS Control Panel is equipped with a graphic display and a systern of indicators (annunciators) and alarms co indicate abnormal or undesirable process conditions. LWTS System logic is controlled using a Programmable Logic Controller (PLC). LWTS Cperations Personnel have telephone communications available to STS Operations Control. LWTS and CSS operations Personnel share a common control room. LWTS instrumentation and controls exist such that the system may be safely operated, monitored and shut down i 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 cond!tior.s 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 nwnber 812 is for emergency use only. 11 . 5 . 4 . 8 FIRE AND EXPIDSION PROTECTION SYSTEM There is no potential for explosion in the LWTS. The LWTS is equipped with fire detection equipment, alarm systems, and suppression systerns commensurate with its needs as determined by the West Valley Nuclear Services Company, Incorporated (WNS) Radiation and Safety Group. Fire fighting procedures for LVIS conform to existing WNS procedures and TR GP-16. CAF0778:3RM 32
WNS SAR.005 Rev. 3 Tte only identifiable potential fire hazards in the LVTS System are electrical insulstion, 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 flanaable material; however, the event is considered unlikely, XC3 and other areas where LVTS components are housed are constructed of concrete and steel. All LVTS process components are manufactured from nonflammable materials. 11one of the above mertioned potential fire hazards are considered to be a high risk hazard. Due to the low potential fire hazard in the process cells during LWTS operations, these are not equipped with fire detection and protection equipment. The LVTS control room is equipped with a wet pipe sprinkler system. The LVTS control panels are equipped with fire detectors and halon extinguisher. l 11 . 5 . 4 . 9 MAINTF. NANCE SYST}RS LWTS systems and couponents are installed in decontaminated process cells O (XC3, ppC, etc.) and have a design life of ten (10) years. Equipment such as valves, pumps, and instrumentation which may require periodic servicing or repair are designed to be remotely flushed with clean water prior to contact maintenance. Where possible, these components are located away from high radiation sources to reduce potential exposure to personnel from other process components, piping, valves, and pumps are designed to be self draining to the maximum extent possible. Most valves within XC3 which are located in high exposure rate areau are equipped with remote manual operators in the event of actuator failure or malfunction. All maintenance work is performed in accordance with WDp 010 " Radiological Controls Manual" and WDp-Oll " Industrial Health and S2fety Manual." In the operational phase, AIARA is maintained by having the ability to flush lines, and by placement of components which may require repair or servicing in " low" I exposure rate areas. Temporary shielding is also used to support maintenance activities. CAF0778:3RM 33 J
WNS SAR 005 Rev. 3 O H.5.4.10 cola citEMICAL SYSTDtS A chemical feed systers is located in LXA, It consists of storage tanks and positivo displacernent pumps to feed acid (l(NO3 ) or caustic (Naoll) as needed to support processing of waste streams. Demineralized water is available to t flush process lines of residual acid or caustic. The Chemical Feed Systern has the ability to add acid or caustic to Tanks 7D 2, $Di$A1, $D15A2 and $D15B. Potential abnormal events and accidents concerning the system are addressed in Section H.9.7. O l l l. CAF0778:3RM 34 _ . _ . , , . . . , . , . , ., , , , _ . , , . . , _ _ . . , , . . . , , , ,m_.-,.,-,,o._,._,_.... .,w
WNS SAR 005 Rev. 3' s REn3tENCES }VR SECT 10N_Il 2 LO, j American National Standards Institute. A58.1. 1982 Minimum Design Load for Buildings and Structures. WNS,1986, Design Criteria for t.he Liquid Waste Treatment System, Rev.1, Transmitted 'uy Merno VD:86:0267. l l l 1 l l i ! l l l CAF0778:3RM 35
WtiS.SAR 00$ Hev. 3
- - -TABly.11.5.3 1 . -
IVTS trfil.1TY Hl1611R. M ENTS- -- Electrical kV 480V, 3 (_. 120V, I f. Normal 45 X X Peak 75 X X Emergency 45 NA I NA Rated Flow Rate Co,mpressed Air _ Temperature P re s_s ure (psigl [11 t re s/sti_nl Utility, normal 27 C 100 560 Utility, peak 27 C 100 2800 Instrument 27 C 50 1160 Emergency NA 0 0 Steam _ Supply Sa tjara t ed Pressure _(kPa), O low Pressure X 172 liigh Pressure X 1034 Emergency NA 0 Deininerallred Vater Flow Rate (litres /nin) Normal 20 Peak 150 Emergency 0 Coolinr. Water IAT - 5.5 C) Flow Rate (litre gmp l Normal 946 Peak 1200 Emergency 0 0 CAF0778:3RM 36
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WNS-SAR 005 l Rev. 3 l 11 . 6 . 0 LWS PROCESS __SYSTIMS 11 , 6 . 1 WOCFSS,1 ESCRilTION The Liquid Waste Treatment System consis,ts of processing equipment, valves, pumps, instruments, piping and controls which are required to transfer and process various liquid wastes consistent with the other Project Process Systen s (CSS and VF, WDP,1985a and 1985b). The heart of the LVTS Process Systera is a hi l,h ef ficiency waste evaporator which reduces the volume of water in the various types of liquid waste processed. Liquid effluents (evaporator overheads) produced by LVTS are pre-treated by ion exchange prior to transfer to the 02 plant.L'JTS in a strategic systero in that it. receives and processes various liquid wastes and prcr des feed to CSS. In addition, LVTS is designed to provide for limited surge capacities cri temporary storage of liquid waste as nocessary. The following sections describe the 1VTS in detail.
- 11. 6 . 1 . 1 NAPJtATIVE DESCRIPTION r
LVTS can be divided into three processes as follows: [1] Collection, segregation and pli adjustment [2] Evaporation and distillate ion exchange [3] Concentrates collection and transfer to CSS or WTF 11 . 6 . 1 . 1 . 1 Collectton, Segregation _ and pil Adjustment Liquid waste streams can be 2011ceted by one of the following tanks: 35104, SD15B, or 7D 2. Tank 35104 has a capacity of 22,000 litres while 3D15B has a capacity of 56,950 litres. Tank SD15B serves as the primary feed tank for the evaporater via pump 71-P-04. Alternatively, as a backup to Tank SD15B, 35104 can feed the evaporator via Pump 71-P-01. Decontaminated supernatant, the stages of sludge wash solutions and the molter feed concentrator overheads will be pumped into Tank 5D158 and then sent to the evaporator. Tank 7D-2, in addition to being able to receive process liquids, is also
- cross-tied with Tank 35104 to handle surgi. volumes, as mentioned above.
Tank 7D-2 is a primaty collection tank for this system. CAF0778:3RM 37
i 1 WNS-SAR 005 l Rev. 3 ) 1 l 1
\~ ' Liquide can also be collected in Tanks 7D 2 and 13D8 for transfers to the WTF.
A series of valves in the ULO Pump Rcom has been designated as the distribution E manifold. This an.ifold allows for flexible use of Tank 5D15B as follows: c Tank 5015B contents can be directly pumped to the evaporator via Fump 71-P-04 through Valves H 310 avd H 309 o SD15B contents can be pumped to Tank SD15A1 via Pump 71 P 04 through Valve H 300; o 5D15B contents can be pumped to Tank 7D 2 via 35104; and o 5D15B contents can be pumped to Tank SD15A1/A2 via Pump 71-P 04 through Valve H-306. H.6.1.1.2 Evaporation and Distillate Ioa Exchany j As described in Section H.6.1.1.1, process liquids ot!ginate from Tank 5D15B and are pumped to tha evaporator via pump 71-P 04 through Vs1ves H-310 and H-309 and LCV-100. These liquids are in tha enge wf 500 ppm to approximately 40 w/o dissolved solids depending upon ths - atrolling ionic st ecies. If the
.clution is greater than about 40 w/o solics the solution may t e diverted to , CSS without evaporation for confinement in a essent matrix. Additional restrictions on dissolved solids concentrations are imposed by-the CSS Process Control Plan and TR IRTS-5.
l The solutions are-fed to the evaporator from Tank 5D15B or Tank 35104 at a nominal rate of 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 1
l-CAF0778:3RM 38 i
WVNS SAR 005 Rev. 3 tank $D15A1 or 5D15A2 in UPC. The concentrates are then pumped to the CSS (- \s. waste dispensing vessel. Evaporator overheads vapor passes through three (3) reflux inactive bubble cap 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 in case of a high AP across the mesh. In start up mode, evaporator condensates flow to the start-up side distillate surgs-tank via Valve H 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 distillate surge tank via Valve H-145 from which it is pumped-to the zeolite ion exchanger (71-D 003) via Pump 71 P-15. After sampling, the liquid is routed to the Interceptors and then fed to the existing LLWTF (02 -Plant) for further processing and release to the environment. E'sporator distillate-is pumped from the distillate surge tank via Pump.P 15 to s zeolite ion exchanger which is solely devoted to evaporator distillate processzng. This lon_ exchanger is equipped with a differential pressure transmitter across the bed and an effluent radiation monitor. Instrument
-readout and alarms are located on the LWTS Control Panel. Off spec effluent is diverted to Tank SD15B (>5E-03 pCi/mL gross beta) or the Interceptors (>3E-07 pCi/mL gross beta) via the PPC manifold.
I After extended periods of evaporator operation it may be necessary to perform a cleaning operation to remove accumulated solids. The solids increase radiation background near the evaporator, lower its boiling ccpacity and accumulate fissile isotopes in the evaporator scale or sludge-in the bottom head. The Aolids 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. Howevet, approximately one gram per liter
N -of boron (as boric acid) may be added to the nitric acid to act as a neutron - - poison for fissile isotopes which may be present.
CAF0778:3RM 39
WNS-SAR 005 Rev. 3 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 di solved 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 vaste tank (BD-2) af ter pli 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 66% higher if the VOC scrubber and condenser were to become inoperable. Atmospheric dispersion will further reduce the concentrations (well below the applicable threshold limit values-time weighted average) at potential on-site and off-site receptor locations. No inpact on the integrity of the llEPA filters is expectec' 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 environment. The cleaning operation will remove radionuclides held up from other waste streams (mostly decontaminated 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 o'nce over the life of the system. L 1 l O CAF0778:3RM- 40
l WVNS-SAR-005 l Rev. 3 i H.6.1.1.3 Concentrates Collection and Transfer Evaporator concentrates leave the evaporator at approximately 109 C. They are cooled to approximately 35 C in the concentrates cooler and pumped to Tank 5D15Al or SD15A2 for temporary storage. Process control limits for this waste stream are as follows:
-o Liquids in the range of 500 ppm to about 40 w/o (depending upon the ionic species) are concentrated to a maximum of 46 w/o dissolved solids. Lower limits will be imposed on concentrates to be transferred to CSS in order to meet waste form requirements, o A limit of 50 pCi/mL Cs-137 is imposed on concentrates generated in LWTS in order to meet shielding requirements. Much lower limits will be imposed on concentrates to be transferred to the CSb in order to meet waste form requirements.
Concentrates are pumped via Pump 71>P-05 or 71-P-06 through Valves H-301 or H-304 respectively to the CSS Waste Dispensing Vessel in the 01 14 Building for incorporation in cement. H,6.1.2 FIInf SHEETS
~H.6.1.2.l_ Piping. and Instrument Details Figures H.6.1-1 through H,6.1 17 contain the latest revision of the piping and instrument detail drawings which are applicable to the Liquid Waste Treatment System.
H.6.1.3 IDENTIFICATION OF ITEMS FUR SAFETY CONCERNS The Liquid Waste Treatment System's operational objective is to significantly reduce the volume of liquid waste requiring solidification and disposal, q The LWTS is remotely operated from a control room located in the t (V 01'-14 Building addition. Shielded valve galleries and pump niches have been CAF0778:3RM 41 i
- - . _ - -- . ~ _ . . .. .
9 WVHS.SAR 005 Rev. 3 s included in the design to reduce exposure rates in areas where repair or ( )- \_/ - maintenance work must be performed. Major equipment replacement or repair can be supported by complete system flushing to reduce the exposure levels in areas such as XC3, All routinely occupied areas are des.3ned to maintain area exposure rates less than 0,25 mR/hr. All operations and work require proper radiation and safety precautions as specified on Radiation Vork Permits (RWPs) and Industrial Work Permits (IWPs). Piping and the various process components angineered for LVTS provide proper containment of radioactive liquids and solids (resins and filter backwash) during all phases of system operation. The V0G System will ensure confinement of airboine radioactive material and hazardous chemicals from process vessels and tanks throughout the system in the main process. building by maintainin8 various degrees of negative air pressure consistent with the radioactive 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
. s VOC System, to ensure that air leakage is into, rather than out of,
\s potentially contaminated areas. All effluents from the site are monitored to ensure that releases are in compliance with DOE Order 5400.5 (see Section H.8.2.1). This program is described in Section A.8.6 of Volume I, 11 . 6 . 2 PROCESS ClllMISTRY AND PilYSICAL CllEMICAL PRINCIPIIS Waste stream process chemistry can be maintained within applicable process requirements for solidification of waste in CSS or return to the WTF by means of the Chemical Feed System. Depending upon waste pil and sample (tank) volume, positive displacement pumps can add either nitric acid (llNO3 ) or sodium hydroxide:(Na0ll) as required. Chemical additions can be made to Tank 7D2, SD15B, SD15A1 and SD15A2. Precautions are taken to minimize processing batches of waste liquid that contain quantities of organic components which can significantly affect efficient system processing during evaporation, filtration or ion exchange. O. CAF0778:3RM 42
WVNS-SAR 005 Rev. 3 fm 11. 6 . 3 MECllANICAL PROCESS SYSTD4S
\v)
- 11. 6 . 3 . 1 COIS CllEMICAL RECEIVING, llANDLING AND TRANSn2 Two types of cold chemicals are routinely received, handled, and transferred during system operation. Acid and caustic chemicals provide a means of pH adjustment to batches of liquid to be processed by LVTS. The Chemical 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 hard-piped connections to the appropriate stora5e tank under operator control and surveillance,
- 11. 6 . 3 . 2 FEED PREPARATION AND llANDLING Batches of liquid radioactive waste are received into LWTS cankage as described in Section H 6.1.1. The operation is remotely performed and no direct handling is required.
/~'T V 11 . 6 . 4 CllEMICAL PROCESS SYSTEMS
- 11. 6 . 4 . 1 PROCESS SYSTIMS The Chemical Addition System which is used to adjust the pH of batch tanks prior to processing. This process is described in Section H.6.2.
- 11. 6 . 4 . 2 COMPONENT / EQUIPMENT SPARES Replacement parts are carried in sufficient queatity to replace worn and damaged portions of valves and pumps associated with the chemical process systems. These include spare valve internals and actuators of all major sizes of valves installed in the system. In addition, spare seals and diaphragms are warehoused to suppcrt repair and maintenance of the chemical addition pumps. No major component.. are carried in spare since the components are designed and consttacted to last the anticipated life of the system f- (10 years).
CAF0778:3RM 43
WVNS SAR-005 Rev, 3, Draft D 11 . 6 . 5 l'ROCESS SUPPORT SYSTEMS ) Utility Air, Utility Water and Project Electrical Supply are the support systems necessaty to effectively operate LWTS. These systems are described in Section B.S.0 of Volume II. 11 . 6 . 5 . 1 INSTRUMDirATION AND COfGROL SYSTEMS Process instrumentation and control systems are designed and specified to provide the primary indications of of f-standard operating conditicus. __ 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 LUTS: o LUTS is designed with sufficient instrwnentation and controls such that it can be started, operated, monitored, and shut down from a single, centralized 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 have 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 P performance, 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) electronic sensing elements are kept to a minimum due to the environmental conditions. Where possible, level, density and pressure measurements are made by hydraulic or pneumatic probes. CAF0778:3RM 44
_ . . - ~ . - . - . . - . . . - - - -- WNS SAR-005 - Rev. 3 o All effluent release points are monitored and sampled in accordance
'O with ANSI:N13,1 1969 (R1982).
o Provisions are made to obtain representative samples of liquid , radioactive wastes for proper process control, f -o Instrumentation and control systems are redundant where appropriate. Figuren H.6.5 1'and H 6.5 2 show the general diagrams of the LWTS
- Control Panel.
[ H,6.5.2 SYSTEM AND COMPONENT SPARES { Control-panel component spares are carried for a number of indicators,
- . controllers and recorders in. quantities commensurate ~with their importance to I
the operation of LWTS. -Spare cards are also in stock to support continuous PLC operation. -Spare. instruments and components are carried to the extent' l recommended by the-manufacturer to support normal' maintenance and repair. 4 l/. H 6,6. IRTS CONTROL ROON _ Figure =H.6;6-1=shows-a general arrangement; drawing of the Control' Room located in the 01-14~ Building: addition. CSS ard LWTS share this room to control-system operations.._The control panel' layout is-included in Section H.6.5.1. H.6.7__ -INTS SAMPLING AND ANALYTICAL RFI)UIRENENTS AND PROCEDURES Liquid-fed to LWTS from STS.for processing will-be sampled from Tank 8D-3 and ,
- 5D158.-- LWTS product-(concentrates) will be. sampled from TanksL5D15A1 or 5D15A2, These, analyses will support materials mass balance--and criticality considerations for fissile' material being-solidified in a-cement matrix or
- held up in the evaporator (TR-IRTS-11).
All sample lines-can be flushed with' utility or demineralized water as necessary to ensure valid sample results. Detailed sampling requirements for
~L7tS are-listed i'n the'STS/LWTS/ CSS Sampling Plan and LWTS procedures.
.O CAF0778i3RM 45
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WVNS-SAR-005 Rev, 3
- p. REFERENCES 1T)R SECTION 11.6,0 b
American National Standards Institute (ANSI) N13.1-1969 (R1982), Specification and Performance of On Site Instrumentation for Continuously Monitoring Radioactivity In Effluents. Burn, P., 1991, Memo E0:91:0055 to C. C. Baker, "NYSDEC Stack Release Permit Modification for LWTS Evaporator Cleaning," dated April 26, 1991. Saha, A. K., 1986 Document WVNS-PN 003 to Distribution, "LWTS Process Control Interlocks," Rev. O, dated March 19, 1986. WVDP, 1985, Safety Analysis Report, Volume II, Existing Plant and Operations. WVDP, 1985a, Safety Analysis Report, Volume IV, Cement Solidification System.
-s WVDP, 1985b, Safety Analysis Report, Volume III, Vitrification System.
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