ML20077H090

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Predismantling (Post-Fuel Removal) Surface Contamination Survey of AGN-201 Reactor & Facility
ML20077H090
Person / Time
Site: 05000394
Issue date: 07/20/1983
From: Adamson R, Neelands J, Rosen A
CALIFORNIA POLYTECHNIC STATE UNIV., SAN LUIS OBISPO
To:
Shared Package
ML20077H082 List:
References
NUDOCS 8308090597
Download: ML20077H090 (3)


Text

c Pre-Dinmentling (Post-Fuel Remwal) Surface Contaudnation Survey of the AGle-201 Reactor and Facility July 20, 1983 by:

R. Adamson, Reactor Administrator J. Neelands, Technician A. Z. Rosen, Acting Radiation Safety Officer l

l l

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l 0300090597 830004 PDR ADOCK 05000394 W

PDR.

' ~ ~ - " ~ ~ ~ -

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The following surveys were conducted:

1. Quema Sirveys Numbered survey points are shown on the attached Figures 1, 2 and 3.

Instrument: Ludlum Model 125 - Micro-R meter, calibrated 12/4/82 A. Area Sirvey Results (See Figure 1 for ntmbered positions)

(Except as noted, all surveys were done at waist-height.

All readings include background - 8 to 10 pR/hr.)

Position Gama Readings (pR/hr)

(1) on surface 7

(2) 9 (3) 9 (4) 8 (5) 8 (6) at center of safe 8

(7) on surface 8

(8) on surface 7

(9) 8 (10) on surface 8

(11) centerline of reactor 7

(12) centerline of reactor 7

B.

Reactor 21rvey Hesults (See Figure 2)

Position Gama Readings (pR/hr)

(13) inside water tank 6

(14') at top surface of reactor 8

(14) inside graphite liner 35 (15') at bottom surface of thermal column 35 (15) 1 m below bottom surface of thermal column 10 (16) control rod access tank (center) 8 C.

Core S1rvey Results (See Figure 3)

Position Gama Readings (pR/hr)

(17) at surface of graphite (bottom) 14 (18) at surface of graphite (side) 23 (19) at tank surface (bottom) 10 (20) at tank surface (top) 10

J

2. asuvable Cbntaunination Alpha symbols (A through FF) show where wipes were made on Figures 1, 2 and 3.

Instrument: Eberline " Rascal" PRS-1, S/N 493; Alpha / Beta Probe 210, calibrated 7/26/83.

Background Reading 46 12 CPM. Wipes were made over 100 cm2 area unless otherwise noted.

Overall detection efficiency for:

Alpha (AM-241 standard) 10%

Beta ('10-99 standard) 8%

(combined efficiency used is 10%)

Position Count Rate (CPM)

(CR-BR)

Max DPM A-Sides of graphite liner in 46 0

B in reactor tank (Fig. 2) 45

-1 C

42

-4 D.

48 2

20 E

Graphite inserts (Fig. 2) 46 0

F~

" Green" control

'inside 44

-2 G

rod holder

_outside 53 7

70 H

- graphite spacer 69 23 230 I"

" Orange" control

'inside 45

-1 J

rod holder

.outside 49 3

30 K.

- graphite spacer 59 13 130 L'

"Furple" control

'inside 48 2

20 M

rod holder

.outside 50 4

40 NJ

- graphite spacer 55 9

90 O'

Fine control

'inside 50 4

40 P

rod holder

.outside 46 0

0

- graphite spacer 52 6

60 R-Control rod holes in 57 11 110 S

graphite core (Fig. 3) 45

-1 T

48 2

20 U-50 4

40 V

See Figure 3 62 16 160 W

See Figure 3 49 3

30 X

See Figure 3 45

-1 Y

See Figure 3 48 2

20 Z

See Figure 3 50 4

40 AA See Figure 3 57 11 110 BB Control rod supports (Fig. 2) 49 3

30 CC Internal wall of 43

-2 access port (Figure 2)

DD Inside glory hole liner 44

-1 (Fig. 2) (area 10 cm2)

EE Westinghouse ion chanber 46 0

bottom (area 10 cm2)

FF Bottom surface of thermal 45

-1 colum (Figure 2)

.... - -. -, -., - - - - _ -. - -.. -.. - - -.. -