ML20097J532

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App C to Reactor Decommissioning Rept & Final Status Surveys for Facility
ML20097J532
Person / Time
Site: 05000077
Issue date: 09/22/1995
From:
CATHOLIC UNIV. OF AMERICA, WASHINGTON, DC
To:
Shared Package
ML20097J530 List:
References
NUDOCS 9602020235
Download: ML20097J532 (18)


Text

{{#Wiki_filter:> h 6 APPENDIX C , POWER PLANT-MACHINE SHOP / MECHANICAL ROOM FINAL STATUS SURVEYS

  • Reference Drawings:

Figure C-1 Reactor Room Plan (originallocation) > Figure C-2 Machine Shop Figure C-3 Power Plant-Machine Shop (grid map) Figure C-4 Power Plant-Mechanical Room (grid map) Page j

  • Final Status Survey Plan C-1
  • Floor Surfaces Data C-2 -- C-6
  • Elevated 11orizontal Surfaces Data C-7 i

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i }' 1 , Appendix C  ; FINAL STATUS SURVEY PLAN: POWER PLANT MACHINE SHOP 1.0 - Discussion  ; i ! The approximate 24 ft. X 58 ft. Rectangular room which originally housed the  ! reactor was slightly modified in 1%l by the construction of an intemal floor-to- l

ceiling cement block wall which partitioned off a triangular area used to house new boiler equipment. (See Figure C-1 and C-2.) The remainder of the room was l convened into a machine shop and continues to function in the capacity.  !

[ The machine shop area is occupied and in continuous use with an assonment of general machine shop equipment in place (lathes, drill presses, milling machines, j belt sanders, grinders, table saw). The Power Plant mechahical room contains equipment associated with the power plant.

i 2.0 Survey Design
The physical presence of equipment on the floor in the machine shop and power plant mechanical room, coupled with the continuing use and occupancy of these i 1_ areas will necessitate a modification in survey design.

$ A survey built around the premise that . . . if there was a problem that released  ; 1 radioactive contamination into the room, what would still be there?...will be conducted as follows: l I

The room will be griddled, on a map only (Figures C-3 and C-4), into one meter ,

square block. The " points" formed by the intersecting lines will be used as survey point locations as follows: l

  • Direct Radiation Surveys L At least thirty measurements oflow level radiation fields will be i taken at selected grid points at a distance of one meter from the floor l

l surfaces. Residual radioactivity will be considered acceptable based on the criteria stated in the approved decommissioning plan. l 1 i l

  • Indirect Contamination Surveys At least thiny wipe measurements of 100 cm2 (nominal) will be taken on elevated horizontal surfaces within the rooms. Locations will be referenced to the floor grid map, Figures C-3 and C-4. At least thiny wipe measurements will be taken on the lower surfaces

! (floors and walls up to two meters.) ]

  • Direct Contamination Surveys i At least thiny one-minute readings will be taken for fixed beta / gamma contamination levels at selected floor grid points.

Locations will be referenced to the floor grid maps. Residual radioactivity for direct and indirect contamination will be considered acceptable based on criteria stated in the approved decommissioning plan. -j i

                                                                                                                        ]

C-1

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Powgr Plant D&D Survey Data POWER PLANT DECOMMISSIONING SURVEY Machine Shop Floor Removable Contamination Survey Flued Contamination Survey i Alpha Bote Alpha Beta Alpha Beta _' _ _ _ Gamma  ; Locaton Smear # c4wn/100 cm' W100 cm' cpm cpm dpm/100 cm' dpm/100 cm' pR/hr A4 1 0 0 2 41 Bkgd Skgd NT A-1 2 0 1 8 45 43 Bkgd NT A2 3 0 1 2 51 Bkgd 292 NT A3 Not Accessible Not Accessitne NT A4 Not Accessible Not Accessible NT  ! A5 Not Accessible Not Accessible NT A4 Not Accessible Not Accessible NT A-7 4 0 0 3 40 Bkgd Bkgd NT A-8 5 1 0 3 41 Bkgd Bkgd NT A-9 6 0 0 5 41 17 Bkgd NT A 10 Not Accessible Not Accessible NT A 11 7 0 1 5 41 17 Bkgd NT j A 12 8 0 0 4 50 9 243 NT A 13 9 0 0 3 34 Bkgd Bkgd NT - A 14 10 0 0 4 41 9 Bkgd NT A-15 11 0 1 3 52 Bkgd 341 NT f A 16 12 0 0 9 41 51 Bkgd NT i A 17 13 0 0 4 d6 9 49 NT B0- Not Accessible Not Accessible NT B-1 14 0 0 5 60 17 730 10 B2 15 1 1 0 50 Bkgd 243 10 B-3 16 0 0 3 49 Bkgd 195 10 B-4 17 0 0 2 37 Bkgd Bkgd 8 B5 18 0 0 4 36 9 Bkgd 8 E6 19 0 0 3 43 Bkgd Bkgd 8 i

           &7             M                  0               0                              7            M                   M         E%                   9
&8 21 4 0 2 M E% k% 7 E9 3 0 0 0 M &% &@ 8 B 10 Not Accessible Not Accessible 9 j B 11 23 l 4 l 0 9 l 40 l 51 l Skgd to l
B 12 Not Accessible Not Accessible 9 B-13 24 0 0 0 41 Bkgd Skgd 7 B-14 25 0 1 2 47 Skgd 97 8 B 15 26 0 2 3 34 Bkgd Bkgd 8 t B 18 27 0 0 0 45 Bkgd Bkgd 7 l' B-17 28 0 0 3 46 Bkgd 49 NT ,
Meter Model Serial # Probe Type Radalon Calh Date Bkgnd Emciency Probe Size 4

L-2221 89645 sanHator a 08/3145 3 cpm 23.50 % 50cm' L-2221 89828 gm pancaka p 08/30/95 45 cpm 1325% 15.5 cm' L 19 75509 Nel y 08/1745 7 pR/hr N/A N/A T 1500B T-3 gas prop. oAp 05/24/95 .5 & 1.3 cpm 34 & 35 % N/A Skgd = Activity indistinguishable from Background NT = Not Taken. Gamma survey location was not accessible, or was less than one meter from a wall. 4 C-2

i Power Plant D&D Survey Data j 1 POWER PLANT DECOMMISSIONING SURVEY Machine Shop Floor (Continued) Removable Contamination Survey Fixed Contamination Survey l Alpha Beta Alpha Beta Alpha Beta Gamma 1 8 Locatkri Smear # dpm/100 cm' dpm/100 crn' cpm cpm dpm/100 cm dpm/100 cm' pR/hr GO Not Accessible Not Accessible NT  ; C1 29 0 1 1 39 Skgd Bkgd 10 C2 30 0 0 2 58 Bkgd 633 10 l C3 31 0 0 2 47 Bkgd 97 11 l C-4 32 0 1 1 51 Bkgd 292 10 C5 33 0 0 1 62 Bkgd 828 8 l C-6 34 0 0 2 43 Bkgd Bkgd 10 C7 35 1 0 2 46 Bkgd 49 8 C-8 36 4 0 1 50 Bkgd 243 9 C9 37 0 0 3 41 Bkgd Bkgd 9 C-10 38 1 1 4 41 9 Skgd 9 l C-11 39 0 0 2 49 Bkgd 195 9 l C-12 40 0 0 2 48 Bkgd 146 8 C 13 41 0 0 5 28 17 Bkgd 9 C 14 42 0 0 6 32 26 Bkgd 9 C 15 43 0 0 4 56 9 535 8 C-16 44 1 0 0 45 Bkgd Bkgd 9 C 17 Not Accessible Not Accessible NT I I I I I D-0 Not Accessible Not Accessible NT D1 45 0 0 5 35 17 Bkgd 9 D-2 46 0 0 4 53 9 389 9 D-3 47 0 0 2 30 Bkgd Bkgd 10 D-4 Not Accessible Not Accessible NT D5 _ Not Accessible _ Not Accessible NT D6 Not Accessible Not Accessible 9 D-7 48 1 0 4 31 9 Bkgd 8 D8 49 0 0 3 51 Bkgd 292 8 D9 50 0 0 3 48 Bkgd 146 8 D-10 51 0 0 3 34 Bkgd Bkgd 8 D 11 52 0 0 3 43 Bkgd Bkgd 9 D-12 53 1 0 4 40 9 Bkgd 9 D 13 54 2 1 2 39 Bkgd Bkgd 7 D 14 Not Accessible Not Accessible NT D 15 Not Accessible Not Accessible NT D 16 55 0 1 7 42 34 Bkgd NT Meter Model Serial # Probe Type Radaton Calib. Date Bkgnd Emciency Probe Size L 2221 89645 scintillator a 08/31/95 3 cpm 23.50 % 50 cm' L-2221 89628 glipancake p 08/30/95 45 cpm 1325% 15.5 cm' , L 19 75509 Nai y 08/17/95 7 pR/hr N/A N/A  ! T 15008 T-3 gas prop. a& 05/2495 .5 & 1.3 cpm 34 & 35 % N/A , Bkgd = Activity indistinguishable from Background j NT = Not Takes Gamma survey location was not accessible, or was less than one meter from a wall. i l C-3 i

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Powar Plant D&D Survey Data POWER PLANT DECOMMISSIONING SURVEY Machine Shop Floor (Continued) Removable Contamina6on Survey Fixed Contamination Survey Alpha Beta Alpha Beta Alphe Beta Gamma < Locakm Smear # dpm/100 cm' dpm/100_cm a cpm cpm dpm/100 cm' dpm/100 cm' pR/hr E4 Not Accessible Not Accessible NT E1 56 0 0 1 37 Skgd Bkgd 8 E-2 57 0 0 2 44 Bkgd Bkgd 11 E-3 58 0 0 0 51 Skgd 292 9 E4 W 0 0 4 4 9 &% 8 E-5 60 0 0 2 52 Bkgd 341 9 E-6 61 2 0 1 32 Bkgd Bkgd 8 E-7 62 0 0 1 44 Bkgd Bkgd 9 E8 63 0 0 3 69 Bkgd 1168 8 E-9 64 0 0 1 50 Bkgd 243 8 E 10 65 6 3 5 24 17 Bkgd 8 E-11 66 0 0 2 46 Bkgd 49 9 E 12 67 0 0 3 36 Okgd Bkgd NT E 13 Not Accessible Not Accessible I I I I I F0 Not Accessible Not Accessible NT F-1 68 1 1 1 36 Bkgd Bkgd 9 i F-2 69 1 0 1 63 Bkgd 876 10 F3 70 0 0 3 36 Bkgd Bkgd 9 F4 71 0 0 4 34 9 Bkgd 9 F5 72 0 0 1 46 Skgd 49 9 F-6 73 0 0 3 45 Bkgd Bkgd 9 F-7 74 0 1 3 46 Bkgd 49 10 F-8 75 0 1 4 32 9 Bkgd 7 F-9 76 1 0 2 29 Bkgd Skgd 8 F-10 77 0 0 4 41 9 Bkgd 8 F-11 78 0 0 4_ , 47 9 _ __97 _ _ 7 G4 M 0 0 2  % &% &% NT G1 80 0 0 0 36 Bkgd Bkgd to

G-2 81 0 0 4 44 9 Bkgd 10 G-3 82 0 0 6 59 26 682 10 G-4 83 0 1 1 47 Bkgd 97 9 45 N 0 0 2  % &% &% 8 G-6 85 1 0 2 35 Bkgd Bkgd 7 G7 86 0 0 3 31 Bkgd Bkgd 8 G-8 Not Accessible Not Accessible 9 G-9 Not Accessible Not Accessible NT l

G-10 87 0 0 2 33 Bkgd Bkgd 10

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G 11 88 0 0 4 59 9 682 10 j l Meter Model Serial # ProbeType RadatKm Cahb. Dans Bkgnd Effciency Probe Size L-2221 89645 scintillator a 08/3195 3 cpm 23.50 % 50 cm' L-2221 89628 gm pancake 08/30/95 45 cpm 1325% 15 5 cm' L-19 75509 Nel y 08/17/95 7 pR/hr N/A N/A T 1500B T-3 gas prop. a& 05/2495 .5 & 1.3 cpm 34 & 35 % N/A Bkgd = Activity indistinguishable from Background NT = Not Taken. Gamma survey loca6on was not accessible, or was less than one meter from a wall. C-4

    ,      .                                          Power Plant D&D Survey Data POWER PLANT DECOMMISSIONING SURVEY Machine Shop Floor (Continued)

Removable Contaminetton Survey Flued Contamination Survey Alpha Beta Alpha Beta Alpha Beta Gamma Locaton Smear # dpm/100 cm' dpm/100 cm' cpm cpm dpm/100 cm' dpm/100 cm' pR/hr H-0 Not Accessible Not Accessible NT H-1 Not Accessible Not Accessible NT H2 89 l 0 l 0 4 l 51 l 9 l 292 NT H-3 Not Accessible Not Accessible NT H-4 Not Accessible Not Accessible NT H-5 90 l 1 l 0 2 l 41 l Okgd l Skgd NT H6 Not Accessib's Not Accessible NT H-7 91 0 0 2 44 Bkgd Bkgd NT 48 W 1 1 3 M E@ &% NT H-9 Not Accessible Not Accessible NT H-10 93 0 0 1 38 Bkgd Bkgd NT H-11 94 0 2 3 35 Bkgd Bkgd NT Meter Model Serial # Probe Type Radabon Calib. Date Bkgnd Emesency Probe Size L 2221 89645 scintillator a 08/31 S 5 3 cpm 23.50 % 50 cm' L-2221 89628 gn pancake p 08/30/95 45 cpm 1325% 15.5 cm' L-19 75509 Nel y 08/17BS 7 pR/hr N/A N/A T 15008 T-3 gas prop. a&S 05/2445 .5 & 1.3 cpm 34 & 35 % N/A Bkgd e Activity Indistinguishable from Background NT = Not Taken. Gamma survoy locanon was not accesalble, or was less than one meter from a wall. I l I I i i l J C-5 1

Pow;r Plant D&D Surv:y D:ta POWER PLANT DECOMMISSIONING SURVEY Mechanical Room Floor Removable Contamination Survey Flued Contamination Survey Alpha Beta Alpha Beta Alpha Beta Gamma l.oceton Smear # dpm/100 cm' dpm/100 cm 8 cpm cpm dpm/100 cm' dpm/100 cm' R/hr B3 A1 0 1 3 39 Skgd Bkgd NT B-4 1 0 0 3 38 Bkgd Bkgd 11 B-5 2 1 2 2 63 Bkgd 876 NT NT _ 00 A2 0 0 1 44 44 Bkgd Bkgd Bkgd C1 3 0 0 2 Bkpd 11 C2 4 0 0 4 37 9 Bkgd 10 C3 5 0 0 3 45 Bkgd Bkgd 11 C-4 6 0 1 2 43 Skgd Bkgd to C-5 7 1 2 3 49 Bkgd 195 11 D-0 A-3 0 0 0 36 BkDd Skgd NT D1 8 0 0 3 55 Bkgd 487 to 0-2 9 1 1 4 39 9 Bkgd 11 0-3 A-4 0 0 4 42 9 Bkgd NT D-4 10 0 1 4 36 9 Bkgd 11 D-5 11 0 0 2 33 Bkgd. Bkgd 11 E4 A-5 0 _0 0 44 Bkgd Bkgd NT E1 12 0 1 7 51 34 292 NT E2 13 0 0 2 42 Bkgd Bkgd NT E-3 14 0 0 4 32 9 Bkgd NT E-4 15 2 0 3 28 Bkgd Bkgd NT E-5 16 0 0 0 41 Bkgd Bkgd NT Meter Model Serial e Probe Type Radation Calib. Date Bkgnd Efficiency Probe Size L 2221 89645 scintillator a 08/31/95 3 cpm 23.50 % 50cm' 89628 gm pancake p 08/30/95 45 cpm 1325% 15 5 cm' J 2221 L 19 ,. 75509 Nel y 08/17/95 7 pR/hr N/A N/A yl T 1500B l T-3 gas prop. a& 05/24/95 .5 & 1.3 epm 34 & 35 % N/A Bkgd a Activity indistinguishable from Background NT = Not Taken. Gamma survey locason was not accessible, or was less than one meter from a wall. C6

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 )                                                                                           Pow:r Plant D&D Survsy Data POWER PLANT DECOMMISSIONING SURVEY
^

Machine Shop, Elevated Horizontal Surfaces l l I I Removable Contamination Survey Locabon Alpha Beta Smear # Descripton dpm/100 cm' dpm/100 cm' 1 Top of pipe at point A 1 0 0 2 Window sill at point A-1 1 1 3 Top of pipe at point A-4 0 0 4 Wridow slil at point A4 0 0 5 Top of gpo at point A4 0 0 6 Ught Fixture at point C 1 0 0 7 Light Fixture at point C-2 1 1 8 Ught Fixture at point C-3 0 0 q 9 Ught Fixture at point C-5 2 1 10 Light Fixture at point C 7 0 0 11 Ught Fixture at point C-9 0 0 12 Ught Fixture at point C-11 0 0 _ 13 Top of pipe at point C 12 0 1 14 Top of pipe at point C 13 0 0 15 Window sill at point C 13 0 1 16 Top of pipe at point C-16 0 1 17 Window sill at point C-16 0 0 18 Top of pipe at point 0-16 0 0 19 Ught Fixture at point F-9 0 0 j 20 Lipit Fixture at point F-7 0 0 21 Ught Fixture at point F-5 2 2 22 Ught Fixture at point F 2 0 0 23 Door sill at point G-0 4 1 _ 24 Electrical conduit at H-2 0 0 25 Electrical conduit at H-4 0 0 26 Electrical conduit at H4 0 2 27 Junction Box at point H-7 0 1 28 Electrical conduit at H-8 0 0 29 Electrical conduit at H 10 0 0 30 Electrical conduit at H 12 1 0 31 Electrical conduit at H 5 0 2 32 Electrical conduit at H 11 0 0 33 Window sill at point A-15 0 0 34 Window sill at point A-10 0 0 35 Vertical pipe joint at A 1 2 1 Meter Model Serial # Probe Type Radabon Calb. Dans Bkgnd Effeiency Probe Size L-2221 89645 scintillator a 08/31 S 5 3 cpm 23.50 % 50cm' L 2221 89628 g11 pancake S 08/30 S 5 45 cpm 1325% 15.5 cm' L 19 75509 Nel y 08/17/95 7 pR/hr N/A N/A T-1500B T-3 _ gas prop. a&p 05/24SS .5 & 13 cpm 34 & 35 % N/A Bkgd = Activity Indistinguishable from Background NT = Not Taken. Gamma survey location was not accessible, or was less than one meter from a wall. i C7

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PAGE l 1 O#UD f

 '                                                                                   TABLE OF CONTENTS                                                                                  !

PAGE l Li s t o f Fi g u res . .. . . . . . . .. . . . .... ..... . . . .. .... ...... .... .... . . . . .. . . . . . . .. . . . . . . . . . . . . . . .. . . i Lis t of G ri d M a ps .. .. . ... .... . . ... . . ....... ..... . . . . .. .. ... .. .... . . . . .. . . . .. .... . . . . ... . ii )

1.0 BACKGROUND

INFORMATION 1.1 Facili ty H isto ry . .. .. .. . .... . .... .. . . .... .. .... .. .. . ........... .... . I  ; 1.2 Facili ty Closure ....... ....... .. .. ......... .. .. .... . . ... ... .. . . .. ... 1 l 1.3 CUA Schedules and Objectives ................... ......... 1-2 1 2.0 SITE DESCRIPTION 2.1 S i te Loc a tio n .. ... .. ..... ....... ......... . . . . .... .. . . . ... . .. .... .... . 2 2.2 Facility Descriptio n ............................................... 2-3 3.0 OPERATING HISTORY 3.1 Ge neral Information .............................................. 3 3.2 Ope ration s Performed ........................................... 3 4.0 DECOMMISSIONING METHODOLOGY 4.1 Objective Impicmentation and Decommissioning A c t i vi ti es . . . . . . . . .. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .. . . . .4. . . . . . . . 4.2 Preliminary S urveys ..... ...... ............... ....... .......... 4 5.0 FINAL STATUS SURVEYS 5.1 S u rvey D es i g n .. .. .. .. .. . .. . .. .. . . . . . . . ... . . . . . . . . . . .. . .. . . .. ... . 5 5.2 S u rvey Rea d i n gs .. . .. .. . . ... .. . . . . .. ... . . . . . . . ... . . . .. . .. . .. . . .. 5 l , 5.3 Final Contamination Measurements ......................... 6 5.4 Exposure Rates at 1 Meter from Floor and Lower Wall S u rfaces.......... .... ............................ 6 5.5 Instrumentation Used ......... ..................... ....... . .. 7  ; 6.0 SURVEY FINDINGS / COMPLIANCE CRITERIA 6.1 Final Status Survey Results ........ ... ................... .. . 7 6.2 Co m pliance Crite ria ... ................. ........ ........ .. .... .... . 7 6.3 Comparison of Final Status Survey Results to Com pliance Criteria ..................................... ......... 8 Appendices: Appendix A Reactor Room Lower Surfaces Data Upper Surfaces Data Structurals Data i Appendix B Reactor Pit Lower / Upper Surfaces Data Reactor Tank (Shell) Appendix C Power Plant Machine Shop / Mechanical Room . Floor Surfaces Data Elevated Horizontal Surfaces Data Revised 9/95

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Iht of Fleures , Figure 1 Location of The Catholic University of America Figure 2 Campus Map General Figure 3 Campus Map - Reactor Location Figure 4 Reactor Room - B16 R Pangborn Hall Figure C-1 Reactor Room Plan - Original Location Figure C-2 Machine Shop I i Revised 9/95

9 d r I ict of Grid Manc

             - Grid Map A-1 Reactor Room                                        j Grid Map B-1 Reactor Pit                                         1 Grid Map C-3 Power Plant- Machine Shop
             - Grid Map C-4 Power Plant- Mechanical Room l

i l l ii Revised 9/95

5.4.2 Establishment of Decommissioning Area External Radiation Exposures l External radiation surveys were conducted in survey units identified in this report as the Reactor Room and Reactor Pit (Appendix A), and (Appendix B),

                        . respectively.

As described in 5.2 a reading was taken centered over each grid block at one meter - above the surface using a micro-R scaled ratemeter. For those floor survey blocks  ; . adjacent to walks, the measurement was taken at the appropriate grid point which maintained a 1 meter distance from the wall. 5.5 Instrumentation Used i Direct Radiation Measurements Ludlum instrumentation Cornoration, Santa Fe, New Mexico 4 ' e Model 3 Survey Meter

e Model 12 Survey Meter e Model 19 Micro R Survey Meter i e Model 43 2 Alpha Scintillation Detector e Model 43-65 Alpha Scintillation Detector l

e Model 44-9 " Pancake" G-M Detector

e- Model 2221 Single Channel Analyzer, Scaler /Ratemeter ,

Indirect Measurements Tennelec. Incornorated, Oak Ridge, Tennessee i e Model LB 5100 Low Background Counting System

6.0 Final Status Survey Results Compared to Compliances Criteria

~ 6.1 Final Status Survey Resuhs i ne final status survey results for the reactor room (Pangbom B16 R), the reactor pit / reactor steel tank, located within this room and the original Power Plant reactor i location have been grouped separately and are attached to this report as Appendices A, B, and C respectively. 6.2 Compliance Criteria ne decommissioning criteria for surface contamination has been established in the decommissioning plan and NRC Regulatory Guide 1.86. The decommissioning criteria for external exposure measured at 1 meter from surfaces has also been , established in the decommissioning plan and for this facility can not exceed 5 i micro-R/ hour gamma above background. 7 Revised 9/95 i

6.3 Comparison of Final Status Survey Results to Compliance Criteria  ; The survey data in Appendices A, B, and C verify that final residual surface contamination and external radiation levels measured at 1 meter from surfaces meet the acceptable compliance criteria as specified in the approved . decommissioning plan and NRC Regulatory Guide 1.86 titled " Guidelines for Decontamination of Facilities and Equipment Prior to Release for Unrestricted Use or Termination of Licenses for Byproduct, Source, or Special Nuclear Material. t b j t 1 3 9 8 Revised 9/95 l

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