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

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l 0300090597 830004 PDR ADOCK 05000394 W

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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)

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