ML20141F231
| ML20141F231 | |
| Person / Time | |
|---|---|
| Site: | Trojan File:Portland General Electric icon.png |
| Issue date: | 06/24/1997 |
| From: | PORTLAND GENERAL ELECTRIC CO. |
| To: | |
| Shared Package | |
| ML20141F210 | List: |
| References | |
| PGE-1061, NUDOCS 9707020164 | |
| Download: ML20141F231 (37) | |
Text
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i n 4
TROJAN NUCLEAR PLANT PGE-1061," Decommissioning Plan" j Revision 3 4
-- The following is provided as a guide for updating PGE-1061, " Decommissioning Plan"--
. REMOVE INSERT i
, Table of Contents - Pages ii-vi, xiii, xiv Table of Contents - Pages ii-vi, xiii, xiv Page1-1 Page 1-1 Pages 2-7 through 2-9 Pages 2-7 through 2-9 l Pages 2-11 through 2-13 Pages 2-11 through 2-13 Page 2-21 Page 2-21 Pages 2-26 through 2-36 Pages 2-26 through 2-36 Pages 2-39 through 2-44 Pages 2-39 through 2-43 Figure 2-1 Figure 2-1 Page 3-44 Page 3-44 Page 3-50 Page 3-50 Page 3-69 Page 3-69 a
9707020164 970624 PDR ADOCK 05000344 W PDR
l TROJAN NUCLEAR PLANT ;
PGE-1061,"Deconunissioning Plan" ,
Revision 3 1
s
- The following is provided as a guide for updating PGE-1061," Decommissioning Plan"-
. I REMOVE INSERT l
l Table of Contents - Pages ii-vi, xiii, xiv Table of Contents - Pages ii-vi, xiii, xiv Page 1-1 Page 1-1 Pages 2-7 th.ough 2-9 Pages 2-7 through 2-9 Pages 2-11 through 2-13 Pages 2-11 through 2-13 Page 2-21 Page 2-21 Pages 2-26 through 2-36 Pages 2-26 through 2-36 i Pages 2-39 through 2-44 Pages 2-39 through 2-43 Figure 2-1 Figure 2-1 Page 3-44 Page 3-44 l l
Page 3-50 Page 3-50 l 1
Page 3-69 Page 3-69 l
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1 O TROMN DECOMMISSIONING PLAN 2.2.4.3 General Decontamination and Dismantlement Considerations . . . . . . . 2-6 2.2.4.4 Decontamination Methods . ... .. ......... ....... ..... 2-8 2.2.4.5 Dismantlement Methods . ........ . ......... ............. 2-9 2.2.4.6 Removal Secuence and Material Handline . . . . . . . . . . . . . . . . . .. . 2-10 2.2.4.7 System Deactivation . . . . . . . . . . . . . . . ... ................... 2-12 2.2.4.8 Ismporary Systems to Sucoort Decommissionine . . . . . . . . . . . . . . . . 2-12 2.2.5 DECONTAMINATION AND DISMANTLEMENT: SYSTEMS, STRUCTURES, AND COMPONENTS . . . . . . . . . . . . . . . . . . . . . . . . . . . 2-13 2.2.5.1 Overview . .............................................. 2-13 2.2.5.2 Reactor Coolant System . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .. 2-13 2.2.5.3 Reactor Vessel Internals . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .... 2-14 2.2.5.4 Reactor Vessel ...................... ...... ............. 2-15 2.2.5.5 S team Generators . . . . . . . . . . . . . . . . . . . . . .................. 2-17 2.2.5.6 Reactor Coolant Pumns . ..................................2-18 2.2.5.7 Pressurizer and Pressurizer Relief Tank . . . . . . . . . . . . . . . . . . . . . . . 2-18 2.2.5.8 Chemical and Volume Control System . . . . . . . . . ... . . . . . . . . . . 2- 18 2.2.5.9 Safety Iniection System . . . . . . . . . . . . . . . . . . . . ...... . . . . . . . . 2- 19 2.2.5.10 Residual He lt Removal System . . . . . . . . . .......... . . . . . . . . . 2-2 0 2.2.5.11 Containment Sorav system . ...............................2-20 2.2.5.12 Comoonent Cooline Water System . . . . . . . . . . . . . . . . . . . . ...... 2-21 2.2.5.13 Service Water System . .................................... 2-21 (mk} 2.2.5.14 Soent Fuel Pool and Fuel Handline Eauiement . . . . . . . . . . . . . . . . . . 2-22 2.2.5.15 Scent Fuel Pool Cooling and Demineralizer System . . . .......... 2-23 2.2.5.16 Condensate Demineralizers . . . . . . . . . . . . . . ................... 2-23 2.2.5.17 Steam Generator Blowdown System ........................ . 2-23 2.2.5.18 Primary Makeuo Water System and Refueling Water Storage Tank . . 2-24 2.2.5.19 Plant Effluent System . . . . . . . . ... . . . . . . . . . . . . . . . . . . 2 -2 4 l 2.2.5.20 Containment Ventilation Systems . . . . . . . . . . . . . . . . . . . . . . . . . . 2 -2 4 l 2.2.5.21 Hydrogen Recombiners .............. ..................... 2-25 2.2.5.22 Fuel Building and Auxiliary Building Ventilation Systems . . . . . . . . 2-26 2.2.5.23 Condensate Demineralizer Buildine Ventilation System . . . . . . . . . . . 2-26 2.2.5.24 Imtrument and Service Air Systern ..........................2-26 2.2.5.25 Gaseous Radioactive Waste System . . . . ... ..... . . . . . . . . . . 2 -2 7 2.2.5.26 Solid Radioactive Waste System .................. .. . .. . 2-27 2.2.5.27 Clean Radioactive Waste System . . . . . . . ........ ........ . 2-28 2.2.5.28 Dirty Radioactive Waste System ..... ....... ...... ..... . 2-28 2.2.5.29 Radiation Monitoring System . .. ... ... ... . . . . . . . . . 2-29 2.2.5.30 Process Samoling System .. .... .. . ................2-30 2.2.5.31 Fire Protection System . ...... ..... .......... . . . . . . . . 2 31 2.2.5.32 Electrical Systems . .. .. . . . .. . .. ... . .. 2-31 2.2.5.33 Containment Building . . ...... . . . . .. 2-32
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0s Q TROJAN DECOMMISSIONING PLAN 2.2.5.34 Auxiliary Buildine Uncludine Pine Facade) . . . . . . . . . . . . . . . . . . . . . 2-33
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2.2.5.35 Fuel Building .. ............................. ....... .. 2-34 L 2.2.5.36 Other Buildings . . . . . . . . . . . . . . . ................. ........ 2-35 2.2.6 DECOMMISSIONING EXPOSURE PROJECTIONS . . . . . . . . . . . . . . . . . . . . 2-36 l
2.2.7 DECOMMISSIONING RADIOACTIVE WASTE PROJECTIONS . . . . . . . . . 2-37 2.3 DECOMMISSIONING ORGANIZATION AND RESPONSIBILITIES . . . . . . . . . . . 2-38 2.3.1 DECOMMISSIONING ORGANIZATION . . . . . . . . . . . . . . . . . . . . . . . . . . . 2-38 2.3.2 REVIEWS AND AUDITS . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2-39 2.4 TRA INING PR OG RAM . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2-3 9 2.4.1 P ROG RAM S . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2-3 9 2.4.1.1 General Emolovee Training . . ..........................2-40 2.4.1.2 Certified Fuel Handler Training ...........................2-41 2.4.1.3 Work-S oeci fic Trainin g . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2-41 2.4.2 TRAINING RECORDS . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2-41 2.4.3 INSTRUCTOR QUALIFICATION . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2-41 2.5 CONTRACTOR ASSISTANCE . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2-41 i 2.5.1 CONTRACTOR SCOPE OF WORK ....... ........................2-41
(- 2.5.2 CONTRACTOR ADMINISTRATIVE CONTROLS . . . . . . . . . . . . . . . . . . . . 2-42 i5 2.5.3 CONTRACTOR QUALIFICATIONS AND EXPERIENCE . . . . . . . . . . . . . . . .- 2 I v
2.5.3.1 G en era l . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2-4 2 2.5.3.2 TL G S e rvi c e s . I nc . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2-42 l
- 3. PROTECTION OF OCCUPATIONAL AND PUBLIC HEALTH AND SAFETY . 3-1 i l
l 3.1 FACILITY RADIOLOGICAL STATUS . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .. 3-1 1 3.1.1 FACI LITY HI STO RY . . . . . . . . . . . . . . . . . . . . . . . . . .. . . . . . . . . . . . . . . . . . . . . 3-1 1 1
3.1.1.1 Ope rati n g H i sto rv . . . . .. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3-1 l 3.1.1.2 Radiolocical Historv . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3-1 3.1.2 CURRENT RADlOLOGICAL STATUS OF TNP . . . . . . . . . . . . . . . . . . . . . . . . 3-3 3.1.2.1 S t ructures . . . . . . . . . . . . . . . . . . . . . . ....... ................. 3-5 3.1.2.2 S ystem s . . . . . . . . . . . . . . . . ............... ... .. ...... . 3-7 3.1.2.3 A ct ivat io n . . . . . . . . . . . . . . . . . . . . . . . . . ...................... 3-8 3.1.2.4 Environment . . . . . . . ... .............. .............. .. . 3-9 3.1.2.4.1 Surface Soil Survey . . . . . . .. ................... 3-10 3.1.2.4.2 Water S urvey . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3- 1 1 3.1.2.4.3 Bottom Sediment Survey . . . . . . . . . . . . . . . . . . . . . . . . 3-12 3.1.2.4.4 Pavement Survey . . . . . . . . . . . . ............. .. 3-13 3.1.2.4.5 Exposure Rate Survey . . . . . . . . . . . . . . . . . . . . . . . . . . . 3-14 1
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J TROJANDECOMMISSIONING PLAN
-3.1.2.4.6 Summary of Environmental Results . . . . . . . . . . . . . . . . . . 3-15 3.1.3 C ONC L USION . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3-15 Appendix 3.1 A, Summary of Notable Radiological Contamination Events . . . . . . . . . . . . 3-17 i Appendix 3.1 B, Summary of Structural Survey Results . . . . . . . . . . . . . . . . . . . . . . . . . . . 3-22 3.2 RADIATION PEDTECTION PROGRAM . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3-37 3.2.1 INTRCDUCTION . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3-3 7 3.2.2 RADI ATION PROTECTION OBJECTIVE . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3-37 3.2.3 RADIATION PROTECTION AND ALARA PROGRAM POLICIES . . . . . . . 3-37 3.2.4 RADIATION PROTECTION ORGANIZATION . . . . . . . . . . . . . . . . . . . . . . . 3-38 3.2.5 MANAGEMENT RESPONSIBILITIES . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3-38 3.2.5.1 General Manager. Trojan Plant . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3-3 8 3.2.5.2 Manager. Personnel / Radiation Protection . . . . . . . . . . . . . . . . . . . . . . 3 -3 8 3.2.5.3 En gineering Management . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3-3 9 3.2.5.4 Managers and S unervisors . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3-39 3.2.6 RADIATION PROTECTION PROGRAM IMPLEMENTATION . . . . . . . . . 3-39 3.2.6.1 Radiation Protection Eauipment and Instrumentation . . . . . . . . . . . . . 3-39 3.2.6.1.1 Laboratory Radiation Protection Instrumentation . . . . . . . 3-40 3.2.6.1.2 Portable Radiation Detection Ins +rumentation . . . . . . . . . . 3-40 3.2.6.1.3 Portable Air Sampling Instrumentation . . . . . . . . . . . . . . . 3-41
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's 3.2.6.1.4 Personnel Radiation Monitoring Instrumentation . . . . . . . . 3-41 3.2.6.1.5 Area Radiation Monitoring Instrumentation . . . . . . . . . . . . 3-42 3.2.6.2 Control of Radiation Exposure to the Public . . . . . . . . . . . . . . . . . . . . 3-42 3.2.6.2.1 Radiological Effluent Monitoring . . . . . . . . . . . . . . . . . . . . 3-42 3.2.6.2.2 Radiological Environmental Monitoring . . . . . . . . . . . . . . 3-43 3.2.6.3 Control of Personnel Radiation Exoosure . . . . . . . . . . . . . . . . . . . . . . . 3-43 3.2.6.3.1 S hie l ding . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3-4 3 3.2.6.3.2 Access Control and Area Designations . . . . . . . . . . . . . . . . 3-43 3.2.6.3.3 Facility Contamination Control . . . . . . . . . . . . . . . . . . . . . 3-44 3.2.6.3.4 Personnel Contamination Control . . . . . . . . . . . . . . . . . . . . 3-44 l 3.2.6.3.5 Area S urveys . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3 -4 5 '
3.2.6.3 6 Personnel Monitoring . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3-45 3.2.6.3.7 Radiation Work Permits . . . . . . . . . . . . . . . . . . . . . . . . . . . 3-45 3.2.6.3.8 Trai ni ng . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3 -4 6 )
3.2.6.3.9 Controls, Practices, and Special Techniques . . . . . . . . . . . 3-46 3.2.6.3.10 Radioactive Materials Safety . . . . . . . . . . . . . . . . . . . . . . . 3-46 3.3 RADIO ACTIVE WASTE MANAGEMENT . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3-48 3.3.1 SPENT FUEL MANAGEMENT PROGRAM . . . . . . . . . . . . . . . . . . . . . . . . 3-48 3.3.1.1 Scent Fuel Management Program Descriotion . . . . . . . . . . . . . . . . . . 3 -4 8 A) t V
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% TROJAN DECOMMISSIONING PLAN 3.3.1.2 Effects of Pennanent Renository Schedule on Soent Fuel Management Plan . . . . . . .................................3-49 3.3.1.3 Licensing Activities to Succort the Soent Fuel Management Plan ... 3-50 3.3.2 RADIOACTIVE WASTE PROCESSING . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3-50 ,
3.3.2.1 Gaseous Radioactivity
.....................................3-50 l 3.3.2.2 Ljauid Radioactive Waste . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3-50 3.3.2.3 Solid Radioactive Waste . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3-51 ,
3.3.2.4 Mixed Wastes . . . . . . . .................................... 3-51 3.3.3 RADIOACTIVE WASTE DISPOSAL . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3-52 l 3.4 E VENT AN A L Y S I S . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3 -54 l 1
3.4.1 OVERVIE W . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3 -54 )
3.
4.2 INTRODUCTION
. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3 -54 3.4.3 LIMITS AND ASSUMPTIONS . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3-56 i 1
3.4.3.1 Radionuclide Release Limits ................................ 3-56 l 3.4.3.2 Assumotions . . . . . . . . ....................................3-57 '
3.4.4 RADIOLOOICAL EVENT IDENTIFICATION . . . . . . . . . . . . . . . . . . . . . . . . 3-58 3.4.4.1 Decontamination Events . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3-59 3.4.4.1.1 In Situ Decontamination of Systems . . . . . . . . . . . . . . . . . . 3-60 3.4.4.1.2 Surface Cleaning Techniques . . . . . . . . . . . . . . . . . . . . . . . 3-62 p}
J g 3.4.4.2 Dismantlement Events . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3-63 L 3.4.4.2.1 Segmentation of Components or Structures . . . . . . . . . . . . 3-63 l 3.4.4.2.2 Removal of Concrete . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3-65 3.4.4.3 Material Handling Events . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3-66 l 1
3.4.4.3.1 Dropping of Contaminated Components . . . . . . . . . . . . . . 3-66 3.4.4.3.2 Dropping of Concrete Rubble . . . . . . . . . . . . . . . . . . . . . . . 3-67 3.4.4.3.3 Dropping of Filters or Packages of Particulate Material . . 3-67 3.4.4.4 Loss of Suncort System Events . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3-68 3.4.4.4.1 Loss of Offsite Power . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3-68 l l
3.4.4.4.2 Loss of Cooling Water . . . . . . . . . . . . . . . . . . . . . . . . . . . 3-69 3.4.4.4.3 Loss of Compressed Air . . . . . . . . . . . . . . . . . . . . . . . . . . . 3-69 '
3.4.4.5 Fi re E vents . . . . . . . . . . . . . . . . . . . . . . . . . ....................370 3.4.4.6 Exolosion Events .. ...................................... 3-71 3.4.4.7 External Events ......... ............................... 3-72 3.4.4.7.1 Earthquake . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3 -7 2 3.4.4.7.2 Flood ing . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3 -7 3 3.4.4.7.3 Tomadoes and Extreme Winds . . . . . . . . . . . . . . . . . . . . . . 3-73 3.4.4.7.4 Volcanic Activity . . . . . . . . . . . ................... 3-74 3.4.4.7.5 Li ghtni ng . . . . . . . . . . . . . . . . . . . . . . ... .......... 3-74 3.4.4.7.6 Toxic Chemical Event . . . . . . . . . . . . . . . . ... . . .. . 3-75 3.4.5 RADIOLOGICAL OCCUPATIONAL S AFETY . . . . . . . . . . . . . . ..... . 3-75
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TROJAN DECOMMISSIONING PLAN t
3.4.6 OFFSITE RADIOLOGICAL EVENTS . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3-76 l 3.4.7 NONRADIOLOOICAL EVENTS . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3-76 i
l 3.5 OCC U PATION A L S AFETY . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3-77 l
3.6 NONRADIOACTIVE WASTE MANAGEMENT . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3-78 3.6.1 AS B ESTO S . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3-7 8 3.6.2 POLYCHLORINATED BIPHENYLS (PCB) . . . . . . . . . . . . . . . . . . . . . . . . . . 3-78 3 . 6.3 M E RC U RY . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3 -7 9
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3 . 6. 4 L E A D . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3 -7 9 1
3.6.5 OTHER PLANT WASTE MATERI ALS . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3-79 1 1
- 4. PROPOSED FINAL RADIATION SURVEY PLAN . . . . . . . . . . . . . . . . . . . . . . . . . 4-1 1
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4.1 INTRODUCTION
. . . . . . . . . . . . . . . . . . . ..........................,....... 4-1 !
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4.2 FINAL RE L E A S E C RITE RI A . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 4-2 l 4.2.1 LIMITS FOR LOOSE AND FIXED SURFACE CONTAMINATION . . . . . . . . 4-2 4.2.2 LIMITS FOR DIRECT EXPOSURE . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 4-2 l 1
- 4.2.3 LIMITS FOR TOTAL CONCENTRATIONS IN SOIL AND WATER . . . . . . . 4-2 l g i 4.2.4 LIMITS FOR UNRESTRICTED RELEASE OF MATERIAL . . . . . . . . . . . . . . 4-3
,.J 4.3 PL ANNING AND DESIGNING THE FTNAL SURVEY . . . . . . . . . . . . . . . . . . . . . . . . 4-4 I 4.3.1 QUALITY AS S URANCE . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 4-4 4.3 .2 T RAINING . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 4 - 5 4.3.3 IN STRUMENTATION . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 4-5 4.3.4 DOC UMENTATION . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 4-6 l
- 5. DECOMMISSIONING COST ESTIMATE AND FUNDING PLAN . . . . . . . . . . . . 5-1 5.1 DECOMMISSIONINO COST ESTIMATE . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 5-1 5.1.1 COST ESTIMATE RESULTS . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 5- 1 5.1.2 COST ESTIMATE DESCRIPTION . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 5-2 5.1.2.1 NRC (Radiological) Decommissioning Costs . . . . . . . . . . . . . . . . . . . . 5-2 5.1.2.2 Nonradiological Decommissioning costs . . . . . . . . . . . . . . . . . . . .... 5-4 5.1.2.3 Soent Fuel Management Costs . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 5-4 5.1.2.4 Emancial Activity Costs . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 5-5 i
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( TROJAN DECOAfAflSSIONING PIAN l LIST OF EFFECTIVE PAGES Section/P_. age Revised Date Title Page June 1996 Pagei December 1996
. Pages ii through vi June 1997 Page vii December 1996 Pages viii and ix June 1996 Page x December 1996 Pages xi through xii June 1996 Page xiii and xiv June 1997 Section 1 Page 1-1 June 1997 Pages 1-2 through 1-7 December 1996 Section 2 Pages 2-1 through 2-6 December 1996 Pages 2-7 through 2-9 June 1997 Page 2-10 June 1996 Pages 2-11 through 2-13 June 1997
,-m Pages 2-14 through 2-20 December 1996 Page 2-21
() Page 2-22 June 1997 December 1996 Pages 2 23 through 2-25 June 1996 Pages 2-26 through 2 36 June 1997 Pages 2-37 and 2-38 December 1996 Pages 2-39 through 2-43 June 1997 Tables 2.2.I through 2.2-4 June 1996 Table 2.2-5 December 1996 Figure 2-1 June 1997 Figures 2-2 through 2-9 June 1996 Figure 2-10 December 1996 Figure 2-11 June 1996 Section 3 Pages 3-1 through 3-30 June 1996 Page 3-31 December 1996 Pages 3-32 through 3-37 June 1996 Pages 3-38 through 3-40 December 1996 Pages 3-41 through 3-43 June 1996 Page 3-44 June 1997 Pages 3-45 through 3-48 June 1996 xiii Revision 3
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Page 3-50 June 1997 i
Page 3-51 and 3-52 June 1996 l
Page 3-53 December 1996 '
Pages 3-54 through 3-68 June 1996 Page 3-69 . June 1997 Pages 3-70 through 3-74 December 1996 Pages 3-75 through 3-79 June 1996 i Tables 3.1-1 through 3.1-4 June 1996 !
Table 3.1-5 Pages 1 of 8 through 7 of 8 June 1996 {
Page 8 of 8 December 1996 l Tables 3.1-6 through 3.1-9 June 1996 ~l Figures 3-1 through 3-39 June 1996 l
- Section 4 June 1996 !
Pages 4-1 through 4-6 June 1996 l Table 4.2-1 June 1996 I Section 5 Pages 5-1 and 5-2 June 1996 Pages 5-3 through 5-9 December 1996 Tables 5.1-1 and 5.1-2 June 1996 Tables 5.31 through 5.3-4 June 1996 -
Section 6 .
Pages 6-1 through 6-3 June 1996 Section 7 Page 7-1 June 1996 Section 8
. Pages 8-1 and 8-2 June 1996 Section 9 Page 9-1 December 1996 Appendix A June 1996
' Appendix B June 1996
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4 TROJAN DECOMMISSIONING PL4N
- 1.
SUMMARY
OF PLAN i
1.1 PLAN AND DECOMMISSIONING ALTERNATIVE This section provides a briefintroduction and overview of the information furnished in the l Trojaa Nuclear Plant (TNP) Decommissioning Plan. l 1.
1.1 INTRODUCTION
l l
2 TNP is located in Columbia County, Oregon, approximatelf42 miles north of j Portland, Oregon. The site consists of approximately 634 acres incorporating a recreational l' area / park, various office buildings, and an industrial area enclosed by a security fence.
TNP is jointly owned by Portland General Electric (PGE),67.5 percent; the City of Eugene,30 percent through the Eugene Water and Electric Board (EWEB); and Pacific Power and .
Light /PacifiCorp (PP&L),2.5 percent. Ownership rights and operation of TNP are definec' in l
" Agreement for Construction, Ownership, and Operation of the Trojan Nuclear Project," dated l October 5,1970. PGE is the majority owner and has responsibility for operating and maintaining l TNP. The Bonneville Power Administration (BPA), a power marketing agency under the United !
States Department of Energy (DOE), is obligated through Net Billing Agreements to pay costs
(,) associated with EWEB's share of TNP, including decommissioning and spent fuel management V costs.
TNP achieved initial criticality in December 1975 and began commercial operation in May 1976. I The reactor output was rated at 3411 MWt with an approximate net electrical output rating of i 1130 MWe. The nuclear steam supply system was a four-loop pressurized water reactor designed by Westinghouse Electric Corporation.
TNP was shutdown for the last time on November 9,1992. On January 27,1993, after approximately 17 years of operation, PGE notified the Nuclear Regulatory Commission (NRC) ofits decision to permanently cease power operations. The owners' decision was predicated on both financial and reliability considerations. The NRC amended the TNP Facility Operating License (NPF-1) to a Possession Only License on May 5,1993.
PGE chose the DECON alternative for decommissioning. Following plant shutdown a transition period of approximately six years is scheduled to allow for decay heat dissipation, prio; to transferring fuel to an Independent Spent Fuel Storage Installation (ISFSI). During the transition period some dismantlement activities may occur. An evaluation of these dismantlement activities will be performed using administrative procedures prior to conducting the activity.
This evaluation process is discussed further in Section 1.4.
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O O TROJAN DECOh!AflSSIONING PLAN Work packages will be implemented in accordance with administrative controls that require evaluations in accordance with the requirements of 10 CFR 50.59.
l Temporary shielding will be used where practical for ALARA purposes during decommissioning activities. Some dismantlement activities may be performed under water for shielding purposes as well as contamination control. l The capability to isolate or to mitigate the consequences of a radioactive release will be maintained during decontamination and dismantlement activities. Isolation is the closure of l penetrations and openings to restrict transport ofradioactivity to the environment. This l consideration should not preclude the removal of penetrations and attachments to contamment, l provided that openings are closed in a timely manner. I Airbome radioactive particulate emissions will be filtered. Effluent discharges will be monitored and quantified. Consideration will be given to the following items:
- 1. Operation of the appropriate portions of the containment ventilation and purge system, or an approved alternate system, during decontaminaticn and dismantlement activities in the Containment Building;
/^) 2. Operation of the appropriate portions of the Auxiliary Building and Fuel Building i V ventilation system, or an approved alternate system, during decontamination and dismantlement activities in the Auxiliary and Fuel Buildings;
- 3. Operation of the Condensate Demineralizer Building ventilation exhaust system i during decontamination and dismantlement activities in the Condensate l Demineralizer Building; and I
- 4. Use oflocal high efficiency particulate air (HEPA) filtration systems for activities I expected to result in the generation of airborne radioactive particulates (e.g.
grinding, chemical decontamination, or thermal cutting of contaminated components).
Work activities will be planned to minimize the spread of contamination. Contaminated liquids will be contained within existing or supplemental barriers and processed by a liquid waste processing system prior to release. To minimize the potential for spread of contamination the following considerations will be incorporated into the planning of decommissioning work activities:
- 1. Isolation of electrical and pneumatic services from components prior to their dismantlement; O
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- 2. Covering of openings in intemally contaminated components to confine internal
( contamination;
- 3. Decontamination and dismantlement of contaminated systems, structures, and components by decontamination in place, removal and decontamination, or removal l l and disposal;
- 4. Removal of contaminated supports in conjunction with equipment removal or decontamination of supports in conjunction with the building;
- 5. Removal of contaminated systems and components from areas and buildings prior i to structural decontamination. (Block shield walls, or portions of other walls, l
ceilings, or floors may be removed to permit removal ofsystems and components.);
- 6. Removal or decontamination of embedded contaminated piping, conduit, ducts, plates, channels, anchors, sumps, and sleeves during area and building structural decontamination activities;
- 7. Consideration oflocal or centralized processing and cutting stations to facilitate packaging of components removed in large pieces; and
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- 8. Removal of small or compact plant components and parts intact, where feasible.
(This includes most valves, smaller pumps, some small tanks, and heat exchangers.
These components could then be decontaminated in whole or part, and reduced to smaller dimensions in preparation for disposal or release.)
2.2.4.4 Decontamination Methods Systems and components that are contaminated will typically be removed and sent to an offsite processing facility, sent to a low-level radioactive waste disposal facility, or decontaminated onsite and released.
Although large scale chemical decontamination is not anticipated as part of the TNP decommissioning, limited application may be used on systems or tanks to reduce radiation dose rates prior to dismantlement or general area decontamination.
Other decontamination methods typically include wiping, washing, vacuuming, scabbling, spalling, and abrasive blasting. Selection of the preferred method will be based on the specific situation. Other decontamination technologies may be considered and used if appropriate.
Applicatio1 of coatings and hand wiping may be used to stabilize or remove loose surface l contaminttion. Airbome contamination control and uste processing systems will be used as necessary to control and monitor releases. If structural attfac',s are washed to remove g
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v) TROJ.4N DECOMMISSIONING PL4N contamination, controls will be established to ensure that waste water is collected in liquid waste processing systems.
Tanks and vessels will be evaluated and, if required, flushed or cleaned prior to sectioning and/or removal to reduce contamination levels and remove sludge. The following considerations vill be incorporated into tank and vessel sludge removal activities:
- 1. Precautions will be made to ensure that liquid inadvertently discharged from the tank is captured in a liquid waste processing system;
- 2. Sludge removed from the tank will be stabilized prior to shipment; and
, 3. Waste water will be processed and analyzed before being discharged.
Concrete that U contaminated or activated may be removed and sent to a low-level radioactive waste disposal facility, allowed to decay below site release criteria, or handled by other methods in accordaace with applicable regulations. Removal of concrete should be performed using methods that control the removal depth to minimize the waste volume produced. Vacuum removal of the dust and debris with HEPA filtration of the effluent should be used to minimize the spread of contamination and reliance on respiratory protection measures.
2.2.4.5 Dismantlement Methods (a)
Dismantlement methods can be divided into two basic types: disassembly, and cutting or other destructive methods. Disassembly generally means removing fasteners and components in an orderly non-destructive manner (the reverse of the original assembly). Cutting methods include flame cutting, abrasive cutting, and cold cuttmg. j i
Flame cutting includes the use of oxyacetylene and other gas torches, carbon are torches, air or oxy are torches, plasma are torches, cutting electrodes, or combinations of these. Most of the torches can either be handheld or operated remotely with the appropriate devices. Abrasive cutting includes the use of grinders, abrasive saw blades, most wire saws, water lasers, grit blast, and other techniques that wear away metal. Cold cutting includes the use of bandsaws, bladesaws, drilling, machining, shears, and bolt / pipe / tubing cutters.
Selection of the preferred method will depend on the specific situation. Other dismantlement technologies may be considered and used if appropriate. Dismantling of systems will include the removal of valves and piping for disposal. Most valves can be removed with the piping. Larger valves and valves with actuators may be removed separately for handling purposes. Valve actuators that can be decontaminated should be removed from the valves prior to pipe removal
- where practical.
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- 4. Auxiliary Building elevator; ,
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- 5. Equipment room monorails; I ;
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- 6. Spent fuel pool bridge crane; and I l i
- 7. Condensate Demineralizer Building bridge crane. I Inspection requirements for the Containment Building Polar Crane, Fuel Building Overhead Crane, Auxiliary Building Electric Holst, Spent Fuel Pool Bridge Crane, and the Condensate I Demineralizer Building Bridge Crane are specified in Trojan Plant Maintenance Procedure MP l l-20," Cranes, Hoists and Winches." Chainfalls and other temporary hoists are inspected and l verified to be in good working condition at the time ofissue from the Tool Room. The Auxiliary Building Elevator is inspected by a State Inspector in accordance with State of Oregon requirements. .
1 The Containment Building polar crane is capable of reaching most locations inside the Containment Building and can handle large, heavy loads. The Fuel Building overhead crane has
, access to a hoistway open to plant grade at the 45 ft elevation. The Auxiliary Building elevator ,
has access to upper floors in the building and can carry small loads. I
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Installed cranes and hoists may be used in conjunction with temporary or mobile lifting and transport devices to support decommissioning. In addition to the use of cranes for general material handling and movement, their use is noted in the applicable component removal
- descriptions.
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The installed plant cranes, hoists, and other lifting devices can be decontaminated and dismantled !
when they no longer are required to support decommissioning activities. I J In areas where considerable material movement is expected, such as the pipe penetration areas, pipeways, and pipe chases, hoisting equipment, such as winches and hoists, may be practical with blocks attached to existing building structural steel. Beam clamps and welded lugs on the steel will allow repositioning of hoisting lines throughout an area.
In some areas of the plant it may be convenient to use material handling equipment, such as forklifts or front-end loaders, for moving materials from one location to another. Small mobile cranes cac be used inside plant structures for smaller equipment and materials. Wheeled carts can also be used for moving pipe, steel, and other items. Skid rails, skid ways, and air pallets may also be used for the movement oflarger equipment.
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l t TROJAN DECOMMISSIONING PLAN b 2.2.4.7 System Deactivation Systems or components will be deactivated prior to decontamination and dismantlement.
In general, deactivation is implemented by mechanical isolation ofinterfaces with operating plant systems, draining piping / components, and de energizing electrical supplies. Combustible l
material (e.g., charcoal from filters, lube oil) is removed from the deactivated components where l l possible. Chemicals used in, or resulting from, decommissioning activities will be controlled in
( accordance with the plant chemical safety program. Plant drawings are revised to indicate deactivated portions of systems. Plant procedures are modified to reflect the changes. l l
Deactivation of plant systems is administratively controlled by approved plant procedures.
Deactivation plans are established to implement the desired system valve lineup changes and electrical isolations. The design change process is used to remove components, lift electrical leads, install electricaljumpers, cut and cap piping systems, or install blank flanges. I Plant procedures provide controls over the operation of deactivated system boundary valves. As additional sy tems are deactivated, existing isolation boundaries are re-evaluated and changed, as necessary, to reflect the new plant condition. Boundary valves are tagged for identification.
2.2.4.8 Temocrary Systems to Suncort Decommissioning 7
(d Decontamination and dismantlement of systems, structures, and components will require removing interferences. Removal of some of these interferences may eliminate power, service air, demineralized water, and other services used for decommissioning. It may also become impractical at some point to continue using installed plant systems. Temporary services and systems can be provided to support decommissioning activities. Temporary modifications to plant structures, systems, and components will be controlled by plant design control procedures.
Portable electric power packs can be powered from motor control centers, load centers, or the yard loop. These portable load centers can supply cutting, hoisting, temporary lighting, or other power needs. Service air can be provided by portable air compressors using hoses or temporary air manifolds. Demineralized water is available from plant tanks, portable demineralizer skids, or portable tankers brought from offsite. Portable hydraulic power centers can be used to power hydraulic equipment.
Temporary liquid and solid waste processing systems may be used during decommissioning for processing plant waste. These systems may be purchased, leased, or built from salvaged plant components. These systems may include filters and/or demineralizers, and may be used at one or more locations in the waste processing path.
Portable radiation monitors and air monitoring equipment can provide localized radiation l monitoring.
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TROJAN DECO &fAllSSIONING PLAN Localized temporary ventilation equipment and HEPA filtration may be used to supplement building ventilation and minimize the spread of radioactive particulate contamination.
2.2.5 DECONTAMINATION AND DISMANTLEMENT: SYSTEMS, STRUCTURES, AND COMPONENTS 2.2.5.1 Overview This section of the Decommissioning Plan presents a brief, general description of TNP systems, components, and structures that are known or considered to be internally contaminated or that may be used to support decommissioning activities. Discussion of activities and tasks associated with decommissioning internally contaminated systems, structures, and components is presented.
Also discussed are systems or components that may be used to support decommissioning.
Because external contamination is generally considered to exist on systems, structures and components located in the radiologically controlled areas (RCAs) of the plant, it is not specifically noted in the following system discussions. However, systems, components, and structures that are extemally contaminated will be decontaminated for release or disposed of as radioactive waste. Plant layout and general arrangement drawings are provided in Figures 2-1 through 2-9.
The considerations identified in this section are based on preliminary planning and will be used during detailed planning in the development of specific work packages. With the exception of f)')
% the removal of the steam generators, pressurizer, and reactor vessel internals, and some dismantlement activities, full-scale dismantlement cf the facility radioactive systems, structures, and components is scheduled to begin after completion of the transfer of spent fuel to the ISFSI.
This section of the Decommissioning Plan describes the major components of contaminated plant systems and, in some cases, a description of equipment removal considerations for system components. The section is intended to provide general information and guidance for work package planning and is not required to be updated to reflect equipment removal. Table 2.2-5 provides a list of major components described in the subsections of 2.2.5 that are removed each year (beginning in 1996).
2.2.5.2 Reactor Coolant System The reactor coolant system (RCS) has four parallel stainless steel piping loops connected to the reactor vessel. The major components of the RCS are the reactor vessel, four steam generators, the pressurizer, four reactor coolant pumps, and associated valves, piping, fittings, and instrumentation. The removal of the reactor vessel is addressed separately in Section 2.2.5.4.
The RCS is located inside the Containment Building. The system is not required to support decommissioning or safe spent fuel storage. The system is internally contaminated. The following specific considerations apply.
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/O Q TROJAN DECO &fMISSIONING Pl.AN The containment spray cumps can be removed intact or separated from their motors. The spray headers, spray nozzles, ad other piping at the 205 ft level inside Containment can be removed by using the polar crane trolley as a platform. Pipe sections may be light enough to be rigged, using relatively lightweight rigging, and lowered to the 93 ft elevation of the Containment Building for removal. Scaffolding can be erected to access sections ofpipe supported and routed up the Containment wall.
Removal of the sodium hydroxide tank intact would require removal ofits cubicle walls and an obstructing motor control center. It may be more practical to remove the tank by sectioning in place and removing the pieces.
2.2.5.12 Comoonent Cooling Water System The component cooling water (CCW) system consists of three pumps, two surge tanks, two main heat exchangers, a chemical addition tank, equipment heat exchangers, and associated valves, piping, fittings, and instrumentation.
The CCW heat exchangers and pumps are located on the 45 ft elevation of the Fuel Building.
The surge tanks are located on the 77 ft elevation in the pipe penetration area. Portions of the system support spent fuel cooling and are required until the fuel is moved to the ISFSI or G alternate cooling is established. Portions of the system have detectable !evels ofintemal V contamination. The following specific considerations apply.
Existing tube pulling openings in the wall north of the CCW heat exchangers can be enlarged, or the wall entirely removed, to allow passage of the heat exchanger into the Fuel Building crane bay. The CCW pumps can be removed after the heat exchangers are cleared. The CCW surge tanks can be removed by enlarging the stairwell openings in the pipe penetration area for rigging, or by sectioning in place.
2.2.5.13 Service Water System The service water system supplies raw water from the Columbia River via the intake structure to the component cooling water heat exchangers, essential room coolers, emergency male-up to the spent fuel pool and component cooling water system, and other equipment. The system has three service water pumps, two service water booster pumps, equipment heat exchangers, and I associated valves, piping, fittings, and instmmentation.
The service water system pumps are located in the intake structure. Portions of the service water system support spent fuel cooling and will be required until the fuel is moved to the ISFSI or attemate cooling is established. This system may also be required to provide dilution for liquid radwaste discharges. The system is not intemally contaminated, but room and equipment coolers in contaminated areas of the plant may have extemal contamination.
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TROJAN DECOMMISSIONING Pl.AN The hydrogen recombiners have been removed to support the removal of the steam generators and pressurizer.
2.2.5.22 Fuel Building and Auxiliary Buildine Ventilation Systems The Fuel Building and Auxiliary Building ventilation systems provid: for the supply, heating, cooling, and exhaust of air for the Fuel and Auxiliary Buildings. The systems include several subsystems: Fuel and Auxiliary Building supply system, Fuel and Auxiliary Building exhaust system, spent fuel pool exhaust system, maintenance area supply cooling system, space heating system, radioactive waste annex supply and return, pump cooling units. Air is exhausted through the primary vent stack which is attached to the outside of the Containment Building. Exhaust air is monitored for radiation. The other systems provide heating and cooling for specific areas in the buildings.
The Fuel and Auxiliary Building ventilation systems are located inside the Fuel and Auxiliary Buildings. Portions of the systems will be used to maintain a habitable environment and control contamination during decommissioning. The systems are intemally contaminated. The following specific considerations apply.
The systems will remain in service until:
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D (V 1. The individual system or component has been evaluated as not required to support further decommissioning activities; or
- 2. An alternate system has been established; or
- 3. Contaminated components have been removed and the building is decontaminated.
2.2.5.23 Condensate Demineralizer Buildine Ventilation System I l
The Condensate Demineralizer Building ventilation system provides for supply and exhaust air I in the building. Supply air is provided through infiltration and, as appropriate, roof supply fans. I Exhaust air is monitored using a sample pump, sample probe, and a radioactive airbome I particulate monitoring filter. I I
The system will remain available for service until the Condensate Demineralizer Building is no i longer used to process radioactive waste, and the building is decontaminated. I 2.2.5.24 Instrument and Service Air System 1 The instrument and service air system supplies compressed air required for pneumatic instruments, valves, and service air outlets throughout the plant. The system has four air 2-26 Revision 3
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TROJAN DECOAfAflSSIONING PLAN compressors, aftercoolers, air receivers, filters, dryers, and associated valves, piping, fittings, and instrumentation.
The instrument and service air system is located in buildings throughout the plant. The system may be used for operation ofcontrol valves, dampers, tools, and breathing air. As a portion of the instrument and service air system is determined not to be required to support further deconunissioning, it may be deactivated and removed. The system is not considered to be internally contaminated.
l 2.2.5.25 Gaseous Radioactive Waste System l The gaseous radioactive waste system, which consists of the vent collection system and the gas collection system, collected and processed gaseous effluents from various tanks, sumps, and plant equipment which contained fluids with entrained or dissolved radioactive gases. The l system contains four waste gas decay tanks, a waste gas surge tank, two waste gas compressors, a l -
vent collection header exhaust fan, and associated valves, piping, fittings, filters, and instrumentation.
The gaseous radioactive waste system is located in the Auxiliary and Fuel Buildings and the Containment Building. The following specific considerations apply.
Tanks should be sectioned to facilitate removal. The waste gas compressors can be d' ismantled into separate components for removal and disposal. The compressor motor can be removed intact or dismantled as necessary to facilitate removal. The gas collection header and vent collection header exhaust filter housings can be removed intact. ,
Temporary filtration and ventilation equipment may be used to provide for venting of required -
tanks to eliminate the need for the vent collection header portion of the system.- Temporary systems to support decommissioning are discussed in Section 2.2.4.8.
2.2.5.26 Solid Radioactive Waste System i The solid radioactive waste system provides for storage and processing for disposal of spent demineralizer resin, expended filter cartridges, and other miscellaneous contaminated solid refuse. The system contains a spent resin storage tank, tiger lock storage tank, spent resin transfer pump, solid radwaste process module, solid waste compactor, spent resin compactor, a filter handling vehicle, and associated valves, piping, and fittings.
The solid radioactive waste system components are located in the Auxiliary and Fuel Buildings.
The solid waste compactor can be used during decommissioning to support packaging of dry l active waste The system is contaminated. The following specific considerations apply.
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The spent resin storage tank and tiger lock storage tank can be sectioned for ease of removal.
System pumps are small and can be removed intact.
1 2.2.5.27 Clean Radioactive Waste System l l l
The clean radioactive waste system was installed to collect, store, process, and dispose of contaminated liquids with low particulate and corrosive chemical content. The system processes ,
water and monitors it during discharge. The clean radioactive waste system consists of the l reactor coolant drain tank, two clean waste receiver tanks, chemical waste drain tank, auxiliary i building drain tank, two treated waste monitor tanks, several pumps, the liquid radioactive waste i ion exchangers, various filters, and associated valves, piping, fittings, and instrumentation.
The clean radioactive waste system is located in the Auxiliary and Fuel Buildings and the l Containment Building. The treated waste monitor tanks may be used for processing radioactive waste water generated during decommissioning activities. The system is intemally 1 cantaminated. The following specific considerations apply. l The reactor coolant drain tank and system pumps are small and can be removed intact. Other system tanks can be sectioned to facilitate removal.
,, Major components of the clean radioactive waste evaporator skid (the vent condenser, distillate
) cooler, evaporator condenser, evaporator, and absorption tower) should be sectioned to facilitate l V removal. The skid mounted pumps and eductor are small and can be removed intact.
Major components of the decontamination system (ultrasonic cleaning tanks, decontamination i catch tank, and spray booth) should be sectioned to facilitate removal. The pressure washer, l workbench sinks, and catch tank pump can be removed intact. l Temporary water cleanup systems may be used to reduce the amount ofinstalled equipment l required to remain operational. The treated waste monitor tanks can operate in conjunction with I the dirty waste drain tank and various sumps to process water used to decontaminate plant buildings or components. Plumbing modifications may be required to use temporary systems.
Temporary systems to support decommissioning are discussed in Section 2.2.4.8.
Radioactive liquid effluents will be monitored and released in accordance with the requirements of topical report PGE-1021, "Offsite Dose Calculation Manual" (ODCM).
2.2.5.28 Dirty Radioactive Waste System 1 The dirty radioactive waste system was installed to collect leakage, drains, reliefs, and condensation within the Containment, Auxiliary and Fuel Buildings for storage and processing. Fluids entering the system are discharged from the plant via the discharge
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l and dilution structure. This system includes Containment Building and Auxiliary Building sumps, sump pumps, dirty waste drain tank, dirty waste monitor tank, filters, and associated piping, valves, and fittings.
l The dirty radioactive waste system components and piping are located primarily in the Auxiliary and Fuel Buildings and the Containment Building, with several floor and equipment drains i
' located within the Main Steam Support Structure. The dirty waste drain tank and the system sumps may be used for processing of radioactive waste water generated during decommissioning activities. The system is internally contaminated. The following specific considerations apply.
l The system tanks should be sectioned to facilitate removal. System pumps are small and can be i
removed intact. The dirty waste bag filter skid will be dismantled and the bag filter housings removed intact. System sumps are concrete pits that will be decontaminated when other decontamination efforts in the various buildings are complete. Techniques for concrete decontamination and demolition are noted in Section 2.2.4.
Temporary water cleanup systems may be used to reduce the amount ofinstalled equipment required to remain operational. The dirty waste drain tank can operate in conjunction with the treated waste monitor tank and various sumps to process water used to decontaminate plant buildings or components. Plumbing modifications may be made to simplify dirty waste drain tank discharge path to the treated waste monitor tank. Temporary systems to support
, decommissioning are discussed in Section 2.2.4.8.
(m") 2.2.5.29 Radiation Monitoring System 1 The radiation monitoring system consists of the process and effluent radiological monitoring systems (PERMS) and the area radiation monitoring system (ARMS). The PERMS were designed to provide monitoring of gaseous and liquid effluent release paths and selected gaseous and liquid plant process systems. A process and effluent radiation monitoring (PRM) system typically consists of an in-line or off line sample chamber, detector, associated process filters, a check source, and other applicable equipment.
The ARMS was designed to provide monitoring of general areas in and around the plant. An area radiation monitor (ARM) channel typically consists of a detector, remote / local alarms, remote / locale indicators, power supply, and a check source.
Portions of the radiation monitoring system are considered to be contaminated. The following specific considerations apply.
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(v) 2 29 Revision 3
(b TROJAN DECOMMISSIONING PL4N The following PERMS channels will be used during decommissioning activities for effluent monitoring. Temporary power or monitoring channels may be used to support decommissioning.
- 1. PRM-9 (liquid radioactive waste effluent discharge) monitors liquid waste effluent during discharges. The Phi may be moved from its current location due to possible discharge line plumbing modifications.
- 2. PRM-2A (auxiliary building ventilation discharge - particulate channel) is designed to monitor the discharge of radioactive particulates through the Auxiliary Building exhaust ventilation stack.
- 3. PRM-1 A (containment building ventilation discharge - particulate channel) is designed to monitor the discharge of radioactive particulates through the Containment Buildir; exhaust ventilation stack.
While spent fuel is in the spent fuel pool, PEDIS channels PRM-2A and Phi-2C (auxiliary building ventilation exhaust low level gas channel) and ARMS channels ARM-12 (fuel building, elevation 93 ft, machine shop access) and ARM-13 (fuel building, elevation 93 ft, new fuel storage area) will be required. Area radiation monitoring will be provided in work areas by temporary monitoring instrumentation, when necessary.
_ PERMS detectors are generally mounted external to piping; thus, they are not likely to be significantly contaminated. The sample tubing and supply piping for PRMs 1 (containment (V) ventilation),2 (auxiliary building ventilation), and 6 (condenser air discharge) is potentially contaminated and will be sectioned as necessary for removal. The skid housings should be dismantled to facilitate removal of various detectors, les d detector housings, and sample piping.
Sample pumps should be removed intact for disposa!.
2.2.5.30 Process Samoling System l The process sampling system provided for collection of samples from the RCS, auxiliary systems and secondary systems. The system includes the primary sampling system, post accident sampling system, automatic gas analyzer, and the secondary sampling system. The system contains small coolers, pressure regulators, relief valves, and associated piping, valves, and fittings.
The process sampling system is not required to support decommissioning or safe spent fuel storage. Portions of the system are internally contaminated. There are no specific considerations.
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() TROJANDECOA1AflSSIONING PLAN 2.2.5.31 Fire Protection System i
The fire protection system provides manual and automatic fire suppression and automatic fire detection for plant areas. The fire protection system includes the following: portable fire i
extinguishers, water supply and distribution systems, fire suppression system, emergency lighting, and the fire detection and alarm system. The main fire pumps are located in the intake structure.
The fire protection system is located in buildings and areas throughout the plant site. The system t is not considered to be internally contaminated. The following specific considerations apply.
Sections of the fire protection system may be d'eactivated and removed from service when no longer required to support further decommissioning activities, or an attemate fire detection and suppression capability has been established. Such changes are changes to the TNP fire protection program, and will be made in accordance with the provision of License Condition C.(8) of Facility Operating (Possession Only) License NPF-1 and 10 CFR 50.59.
The fire protection program is discussed in Section 9 of this plan.
2.2.5.32 Electrical Systems I
, n The electrical system includes the main generator, the switchyard, main and auxiliary ij
' transformers, and the 230 kV ac,12.47 kV ac,4160 V ac,480 V ac,120 V ac,250 V de,125 V de, and lighting distribution systems.
The electrical systems are located in buildings and areas throughout the plant site. Portions of the systems (primarily 12.47 kV ac yard loop,480 V ac, and 120 V ac) may be used to support decommissioning activities. The systems are not considered to be intemally contaminated. The following specific considerations apply.
1 Temporary electrical services may be used as required during decommissioning to facilitate i dismantling and removal of plant components. When a system or component is no longer required, the electrical supply to the component may be isolated and removed. Plant lighting may also be required until building demolition. Lighting and electrical power may be provided by temporary services as discussed in Section 2.2.4.8.
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TROJANDECOAfAflSS10NING PLAN 2.2.5.33 Containment Building i The Containment Building consists of two structures on a common foundation. One is the containment itself; the other is the internal structure, referred to as the containment intemals, whose function is to provide biological shielding. Supports for equipment, operating decks, access stairways, and platforms are included in the containment internals. The two structures are structurally separated above the foundation by a gap based on considerations of maximum relative displacement during an earthquake.
The Containment Building encloses [ed] the reactor, reactor coolant loops, refueling cavity, and portions of auxiliary and engineered safety features systems.
The Containment Building is a fully reinforced concrete structure in the shape of a c71inder with !
a hemispherical roof and flat foundation. The approximate dimensions of the Contamment Building are: 124-ft inside diameter,203-ft inside height,3%-ft wall thickness and 2%-ft dome thickness.
The reactor cavity and instrumentation tunnel are located below the foundation slab. The cylindrical section has a post-tensioning system consisting of vertical and hoop tendons. The dome has a two-way post-tensioning system consisting of hoop tendons and continuous vertical tendons. The inside of the concrete shell is steel-lined. The liner plate is coated with an epoxy-phenolic finish that is approximately 5 mils thick generally to a height of 6 ft above the floors, (o) and 2 to 3 mils inorganic topcoat above that. Penetrations in the Containment Building include the equipment hatch, two personnel air locks, and numerous smaller electrical and mechanical penetrations.
The following specific considerations apply.
Portions of exposed surfaces inside the Containment Building are contaminated. Concrete intemal walls can be decontaminated by water or chemical washing. Surfaces that can not be decontaminated can be scabbled or surface ground down to non-contaminated depths. Portions of concrete stmetures inside the Containment Building (e.g., the primary shield wall) are activated and could require removal oflarge sections of the concrete. This may be accomplished l
by chipping, saw cutting or alternate means. Portions of activated concrete walls may be left in place, provided they meet site release criteria.
Plate steel, structural steel, grating, ladders, and platforms may be decontaminated in place or
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may be removed by unbolting or cutting, and rigged out for decontamination or disposal.
The liner of the refueling cavity will be sectioned for removal. The polar crane or the fuel !
handling crane can be used to lift the sections out. Potential for high levels of contamination $
exist for components removed from the refueling cavity. It may be possible to decontaminate l and release sections of the liners. I I
q V 2-32 Revision 3 1
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( TROJAN DECOA1AllSSIONING PL4N During the removal of the steam generators and pressurizer the tendons were detensioned, a construction opening cut in the side of the Containment Building, and a roll-up door installed in the construction cpening.
2.2.5.34 Auxiliary Building Gncluding Pine Facade) I The Auxiliary Building has two floors below grade, one at grade (elevation 45 ft), and three floors above grade. The portion at or above grade is structurally connected to the Fuel Building on the east and to the Control Building on the west. A number of framing members in the Auxiliary Building are supported by the Containment Building wall.
The exterior walls below grade and slabs are constructed ofreinforced concrete. Interior framing members below grade and framing members above grade are stmetural steel. Exterior walls above grade are generally constructed of concrete masonry block with exterior precast concrete panels (elevation 45 ft) or metal siding at the upper floors. Interior walls are constructed of concrete block masonry. Portions of the Auxiliary Building are coated with an epoxy surface.
The surface is generally applied to the floors and to a height of 12 inches above the floor, but may extend up to 6 ft in corridors and selected rooms.
The Auxiliary Building houses [ed] the following major plant equipment (including necessary
. electrical support equipment):
( 1. Ventilation equipment for the Auxiliary, Fuel, and Containment Buildings;
- 2. Demineralizers and filters;
- 3. Boric acid evaporators; 4
- 4. Volume control tank;
- 5. Service water booster pumps;
- 6. Liquid radioactive waste system tanks and pumps;
- 7. Spent fuel cooling pumps;
- 8. Positive displacement charging pumps;
- 9. Containment spray pumps;
- 10. Safety injection pumps; i 1. Residual heat removal pumps and heat exchangers; C'\
() 2 33 Revision 3
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l TROJAN DECOMMSSIONING PU.V 12.
Waste gas decay tanks, surge tank, and compressors; and l
- 13. Component cooling water pump. 1 Many of the plant components in the Auxiliary Building are located in thick walled cubicles which provided shielding to personnel during plant operation. Notable among shielded components are the ion exchangers and filters located in the demineralizer and filter galleries on the 77 ft elevation. Cell enclosures in this area are concrete masonry walls between 20 and 40 ;
inches thick. Many of the thick shield walls supplement the structural characteristics of the l Auxiliary Building and their removal may require structural analysis.
The Auxiliary Building also contains vertical pipe chases and horizontal pipeways. The function of these features is to provide pathways for routing pipe from components, such as pumps, to heat exchangers or other components or end use points. Piping from multiple systems is frequently routed through common pipe chases or pipeways.
Portions of exposed surfaces in the Auxiliary Building are contaminated. The following specific considerations apply.
The surfaces of walls and slabs in traffic areas have protective coatings. Concrete can be decontaminated by water or chemical washing. Surfaces that can not be decontaminated can be scabbled or surface ground down to non-contaminated depths.
Filter housings can typically be removed from their cells through the filter access plugs at the 93 ft elevation slab and sectioned and reduced, or shipped intact. Piping connections to the filters will be severed using techniques as described earlier.
Demineralizer vessels are relatively inaccessible. Small access ways allow personnel entrance to the cubicles via the valve gallery. Once the resins are removed from the demineralizer vessel and the vessel is rinsed, the vessel can be sectioned in place using techniques described in Section 2.2.4.5. Alternately, openings can be prepared in the slabs or walls for access to the vessel for intact or sectional removal. Removal of entire walls or portions of walls may require evaluation of the building's structural integri.y. Consequently, additional supports or modifications may be required.
2.2.5.35 Fuel Building 1
The Fuel Building contains facilities for storage of new and spent fuel and systems used for processing liquid, solid and gaseous wastes generated by plant operation. It consists of four floors above grade, the spent fuel pool, cask loading pit, new fuel storage pit, cask wash pit, and three reinforced concrete vaults enclosing the CVCS holdup tanks. Portions of the Fuel Building are coated with an epoxy surface. The surface is generally applied to the floor and to a height of l
12 inches above the floor, but extends up to 6 ft in corridors and selected rooms. The walls and l
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() 2-34 Revision 3
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U TROJANDECOMMISSIONING PLAN base slab of the spent fuel pool are constructed of thick (approximately 5 ft to 6%-ft) reinforced concrete. The CVCS holdup tanks are enclosed by walls that are approximately
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2 ft to 2-ft 9-inches thick.
Major pidnt equipment contained in the Fuel Building includes the following items;
- 1. Solid radioactive waste processing equipment;
- 2. CVCS monitor tanks and pumps;
- 3. Seal water heat exchangers;
- 4. Spent fuel pool heat exchangers;
- 5. Boric acid tanks;
- 6. CVCS holdup tanks;
- 7. Component cooling water heat exchangers; and
- 8. Component cooling water pumps.
g Portions of exposed surfaces inside the Fuel Buiiding are contaminated. The following specific considerations apply.
The surfaces of walls and slabs in traffic areas have protective coatings. Concrete can be l decontaminated by water or chemical washing. Surfaces that can not be decontaminated can be i scabbled or surface ground down to non-contaminated depths. Removal of entire walls cr l portions of walls may require evaluation of the building's structural integrity.
2.2.5.36 Other Buildings i The Main Steam Support Structure consists of two floors, one at grade (Elevation 45 ft) and one at Elevation 63 ft. It is located between the Containment Building and Turbine Building and provided protection and support for the main steam isolation, power-operated relief and safety valves, as well as main steam and feedwater piping. The structure is constructed of reinforced concrete and structural steel.
The Condensate Demineralizer Building is a three-story, partially below grade structure located west of the Turbine Building. The building is used for temporary storage and processing oflow- I level radioactive waste prior to disposal. Portions of the building will require decontamination I from radwaste processing activities. I tO 2-35 Revision 3 V
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% TRObtN DECOMMISSIONING Pl.AN_
The Steam Generator Blowdown Building is located south of the Main Steam Support Structure, l
between the Containment Building and Turbine Building. It houses the steam generator l
blowdown tank, heat exchanger, pump, and associated valves and instmments. The building has I a reinforced concrete slab floor, reinforced masonry block walls, and a reinforced concrete roof supported by steel beams and metal decking. The building has a foundation curb designed to contain liquid spills.
1 1
The Radwaste Annex is a single-story windowless structure adjacent to the north wall of the Fuel Building. It is utilized for laundry sorting, storage, and frisking, as well as solid waste compaction and drum storage.
1 The Wright-Schuchart-Harbor (WSH) Warehouse is a Quonset type building that is used to store parts and materials to support plant activities.
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l The Steam Generator Blowdown Building, Main Steam Support Structure, and Radwaste Annex l l are potentially contaminated. I l
2.2.6 DECOMMISSIONING EXPOSURE PROJECTIONS l l
A summary of the projected radiation exposures for the removal of the steam generators and l
, pressurizer, decommissioning activities, and spent fuel management activities is presented in (v) Table 2.2 1. These represent conservative estimates of radiation expcsure.
These estimates are for planning purposes only; detailed exposure estimates and exposure controls will be developed in accordance with the requirements of the Radiation Protection Program (Section 3.2.1) during detailed planning of these activities.
l The estimates incorporate the following assumptions and bases:
- 1. Area dose rates are based on radiological surveys that have been adjusted to account for radioactive decay to the estimated start of decommissioning activities;
- 2. The projected exposure for decommissicaing activities is based on site information:
- 3. The projected exposure for removal of the steam generators and pressurizer is based on detailed project planning;
- 4. Personnel radiation exposure during the transition period (1994-mid 1998) is estimated to be approximately 2 person-rem per year, excluding some dismantlement activities; and
/3 2-36 Revision 3 b
.-.-.-. - - - . - _ - - ~ _ . - - _ _ _ . _ . ~ - . _ - - _ - - . . - - - . - . -
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l TROJAN DECOMMISSIONING PLAN 2.3.2 REVIEWS AND AUDITS The Independent Review and Audit Committee (IRAC) is responsible for reviews and audits in accordance with the TNP Technical Specifications,' Appendix A to Facility Operating j (Possession Only) License NPF-1. The IRAC is responsible for advising the General '
Manager, Trojan Plant on matters relating to safe storage of irradiated fuel. This review and audit function is independent of the line organization responsibilities.
As specified in the TNP Technical Specifications, the Independent Review and Audit l Committee will review and/or audit safety evaluations completed under the provisions of i
10 CFR 50.59, special nuclear material control, radiation protection activities, radioactive waste
- controls, and reportable occurrences. 3 I
2.4 TRAINING PROGRAM The TNP Training Program is designed to provide the necessary instruction to ensure that l
individuals have adequate knowledge and skills to perform theirjob functions safely. Training programs are conducted in accordance with appropriate plant procedures. Initial training programs prepare entry level employees to assume their assigned tasks; retraining programs enable employees to maintain their proficiency.
Individuals requiring access to TNP, including radiologically controlled areas, will receive training commensurate with the potential hazards to which they will be exposed. This applies to PGE employees, contractors, and visitors. J Training applicable to specific activities, tasks, and conditions will be developed or discontinued.
l as appropriate, as decommissioning progresses. Since decommissioning activities will occur while fuel remains stored at TNP, PGE will retain those elements of the TNP Training Program necessary to ensure safe fuel storage and handling, including protection of workers from hazards associated with such activities.
2.4.1 PROGRAMS TNP will maintain training and retraining programs throughout decommissioning as necessary to provide the TNP staff with the specialized training and technica* skills necessary to maintain the plant in a safe condition.
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TROJAN DECOMMISSIONING PLAN 2.4.1.1 General Emnlovee Training i
I Individuals requiring unescorted access to the TNP Industrial Area will receive General l
Employee Training, which includes the following representative topics:
- 1. TNP introduction;
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! 2. Radiological protection fundamentals;
- 3. Emergency response plan; i
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- 4. Plant safety;
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- 5. Fire protection; I
- 6. Chemical safety; ;
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.7. Security;
. l l 8. Quality assurance; and
- 9. Corporate drug awareness.
I Individuals requiring unescorted access to the protected area, RCAs, or the control room will receive additional training, as necessary, in the following topics:
l 1. TNP site specific radiation protection; and 2.' Fitness for duty.
Escorted individuals will receive appropriate training for the areas they will be entering.
l General Employee Retraining is conducted annually and includes subject material from General Employee Training. General Employee Training and Retraining Programs consist oflectures and demonstrations that may be augmented with selected audiovisual aids. The content of the course may be revised, as needed, during decommissioning.
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TROJAN DECOMMISSIONING PLAN 2.4.1.2 Certified Fuel Handler Training l
Training for operators is described in topical report PGE-1057, " Certified Fuel Handler Training Program." The Certified Fuel Handler Training Program is based on a systems approach to l
' training. The program ensures that staff members are adequately trained to perform activities that support the proper handling, storing, and cooling of the fuel.
2.4.1.3 Work-Soecific Training Work specific training for selected activities will include the appropriate level of training in decontamination and other decommissioning activities, health physics, and the use and maintenance of radiation surveillance and monitoring equipment. Cognizant managers will ensure that employees and contractors who perform decommissioning activities are properly trained, qualified, and proficient in the principles and techniques of activities necessary to perform their assigned tasks, in accordance with approved procedures.
2.4.2 TRAINING RECORDS
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Records of training on quality-related activities will be maintained as quality assurance records.
p 2.4.3 INSTRUCTOR QUALIFICATION O
Training may be conducted by PGE employees or contractors. The background, qualifications, and experience ofinstructors will be appropriate for the subject matter. Instructor qualifications are administratively controlled by approved procedures. Instructors are responsible for ensuring training materials are technically accurate and applicable prior to their use or issuance.
Instructors are also responsible for documenting training sessions.
2.5 CONTRACTOR ASSISTANCE 2.5.1 CONTRACTOR SCOPE OF WORK During decommissioning PGE may use contractors to provide specialized services or to supplement the facility staff when warranted. Tasks where contractors may be used to provide support during decommissioning include, but are not limited to, the following:
- 1. Processing, packaging, transportation, and disposal of radioactive material;
- 2. Decontamination and recycling of radioactively contaminated material; j 3. Radiation protection staff augmentation; l
,m I ) 2 41 Revision 3 r
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l TROJANDECOAfAflSS10NING PLAN l kJ l 4. Design and fabrication of special dismantling equipment;
- 5. Engineering and design services such as heavy loads management and transportation engineering; and
- 6. Dismantlement and demolition of components, systems, and structures.
2.5.2 CONTRACTOR ADMINISTRATIVE CONTROLS l
PGE has the responsibility for contractor control, including the contractor's effectiveness in performing to bid specifications. PGE will provide the necessary management oversight to ensure that tasks performed by the contractors are in full compliance with topical report PGE-8010, "PGE Nuclear Quality Assurance Program for the Trojan Nuclear Plant," the purchase agreement, and applicable regulatory requirements.
2.5.3 CONTRACTOR QUALIFICATIONS AND EXPERIENCE 2.5.3.1 General Potential contractors for activities will be required to supply their qualifications as part of bid specifications. These qualifications will be evaluated and reviewed for:
- 1. Demonstrated experience in providing services on similar projects;
- 2. Cost and schedule compliance;
- 3. Technical and operational capability; and
- 4. Ability to meet regulatory requirements.
2.5.3.2 TLG Services. Inc.
TLG Services, Inc. was contracted to perform the TNP Activation Analysis for use in site characterization and Decommissioning Cost Analysis to support the development of the Decommissioning Plan.
I 2-42 Revision 3
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TROJAN DECOMMISSIONING PLAN TLG Services, Inc. is an engineering firm with extensive experience in performing decommissioning cost estimates and other aspects of nuclear facility decommissioning. TLG Services Inc.'s experience includes:
j 1. More than 60 utility and government sponsored decommissioning studies for more b
than 90 units; providing costs, occupational exposure, and waste generation estimates; l
[ 2. Development of NUREG/CR-3587, " Identification and Evaluation of Facilitation l; Techniques for Decommissioning Light Water Power Reactors," June 1986;
- 3. Development ofindustry-accepted reference manual, AIF/NESP-036, " Guidelines to Producing Decommissioning Cost Estimates"; and
- 4. Active participation on four Industry Standards Committees associated with decommissioning.
- 5. Performance of activation analyses for five nuclear facilities.
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l I &g TROJA.V DECOMMISSIONING PUN contamination levels is further controlled and defined in accordance with 10 CFR 20 and radiation protection implementing procedures. Plant procedures also describe the requirements I
for radiological postings advising workers of potential radiological hazards at the entrance and boundaries of radiologically controlled areas.
1 3.2.6.3.3 Facility Contamination Control l l
Plant and radiation protection implementing procedures direct the use of various practices and l equipment to ensure general plant area contamination is controlled at the source to the greatest extent possible. Additional contamination controls are specified forjobs involving high levels of contamination (e.g., a double step-off pad, additional surveys, etc.). Appropriate contamination controls are used when carrying contaminated tools and equipment between areas. Geiger-Mueller count rate meters (friskers) are located within the plant so that personnel can determine if they have been contaminated prior to entering another area of the plant. The j final checkpoint for personnel leaving controlled areas of the plant is the access control point. l Temporary exit points may be established at remote control areas as needed. l Airbome contamination is minimized by minimizing loose contamination levels and their sources. The use ofinstalled and temporary ventilation systems prevents the build-up of air contamination concentrations. These systems are described further in Sections 2.2.4.8, l 2.2.5.20, 2.2.5.22, and 2.2.5.23. I b(N Additional details on the policy and methods for controlling general area and airbome contamination are contained in radiation protection implementing procedures.
3.2.6.3.4 Personnel Contamination Control Contamination of personnel is controlled by the use of several types of protective clothing when entering contaminated areas. In the event that levels of airborne contamination approach or exceed applicable limits, provision is made for personnel to use respiratory protective equipment. Allowances are made for the use of respiratory protective equipment, as specifically authorized by the NRC, in determining whether individuals in restricted areas are exposed to concentrations in excess of the values specified in 10 CFR 20. The use of respiratory protection equipment is consistent with the goal of maintaining the total effective dose to personnel ALARA.
Additional details on the policy and methods for controlling personnel contamination are contained in radiation protection implementing procedures.
l n 3-44 Revision 3
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1 1 g TROJANDECOMMISSIONING PLAN l
3.3.1.3 Licensing Activities to Suncort the Soent Fuel Management Plan l l
4 PGE will file an application for a license for an ISFSI in accordance with 10 CFR 72, Subpart B, which specifies the NRC licensing requirements for the independent storage of spent fuel
- - and high-level radioactive waste. PGE will also petition the State of Oregon to adopt rules i allowing storage of spent fuel in an ISFSI. Transfer of spent fuel and high-level radioactive
, waste from the spent fuel pool to the ISFSI will commence after NRC issuance of the 10 CFR 72 license, and issuance of required State of Oregon approvals.
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- 3.3.2 RADIOACTIVE WASTE PROCESSING i
3.3.2.1 Gaseous Radioactivity j Gaseous radioactivity is expected to be limited primarily to airbome radioactive particulates ,
- generated during decontamination and dismantlement activities. I j Airborne radioactive particulates will be filtered through HEPA filters in the containment ventilation system, the Auxiliary Building and Fuel Bt " tic; vcwn.' tim systems, and the i Condensate Demineralizer Building ventilation system, portio. s of Gb will be maintained in i opemtion during decontamination aad dismantlement activities ir& a .ildings (see Sections )
4 p 2.2.4.3,2.2.5.20,2.2.5.22, and 2.2.5.23). Local temporary ventilation systems with HEPA I
- -( filtration, or other approved alternate systems, may be used in lieu ofor to supplement building ventilation for activities expected to result in the generation of airbome radioactive particulates.
d 4
Radioactive gaseous effluents will be monitored and release limits adhered to in accordance with the methodology and parameters in the ODCM.
3.3.2.2 Liauid Radioactive Waste Liquid radioactive waste will be generated as a result of draining, decontamination, and cutting processes during plant decommissioning.
Portions of the existing iiquid radioactive waste treatment systems (plant effluent system, :
clean radioactive waste system, and dirty radioactive waste system) will be maintained in operation during decommissioning to process liquid radioactive wastes by filtering, demineralizing, and providing for holdup or decay of the radioactive wastes for the
- purpose of reducing the total radioactivity prior to release to the environment (see 4
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)
& TROJAN DECOMMISSIONING PLAN hoisting units be equipped with a holding brake. A holding brake is a brake that auto.natically prevents motion when power is off. The Containment Building Polar Crane, Fuel Buiding Overhead Crane, Auxiliary Building Electric Holst, Spent Fuel Pool Bridge Crane, and 'he I Condensate Demineralizer Building Bridge Crane are equipped with holding brakes. Although I loss of power is not expected to result in crane or hoists failure, this event would be bounded by the material handling events analyses provided in Section 3.4.4.3.
3.4.4.4.2 Loss of Cooling Water 1
Cooling water may be supplied to air compressors and the decommissioning cutting equipment and tools. The following events result from a loss of cooling water:
- 1. Compressed air is lost if an alternate cooling water supply is not established to the I station air compressors within a short time period. The consequences of a loss of i compressed air are presented in Section 3.4.4.4.3; and
- 2. Cutting operations that use cooling water will stop. This does not adversely affect contamination control. ,
1 A loss of cooling water does not result in events leading to a significant release of radioactive j
('} material to the environment during decommissioning activities. Therefore, public health and l
(_/ safety are not adversely affected by a loss of cooling water event.
3.4.4.4.3 Loss of Compressed Air Compressed air is supplied by the station air compressors to operate pneumatic valves and dampers and to power pneumatic tools. The following events occur upon a loss of compressed i air: l
- 1. The liquid discharge control valve for plant effluents fails in a closed position ,
tenninating liquid releases; l
- 2. Decommissioning pneumatic tools shutdown. This terminates potential releases from activities using these tools; and
- 3. Pneumatic ventilation exhaust fan dampers fail in a closed position terminating airbome and gaseous release via those paths. Since this event is not postulated to occur coincident with an event involving abnormal releases of radioactive material, there would be no significant impact on offsite releases.
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