ML20077H090
ML20077H090 | |
Person / Time | |
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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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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
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- 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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