ML20203P265
| ML20203P265 | |
| Person / Time | |
|---|---|
| Site: | 07001359 |
| Issue date: | 08/13/1984 |
| From: | Maschka P IRT CORP. |
| To: | Thomas R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V) |
| Shared Package | |
| ML20203P259 | List: |
| References | |
| NUDOCS 8605060468 | |
| Download: ML20203P265 (29) | |
Text
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.E d l Corporation Ga m 16 P.02 20 Lg 3030 Cattan Road. San Diego. Cahfomia 92121 E-_
619/450-4343. Telex: 69-5412 g
U.S. NRC Region V 1450 Maria Lane Suite 210 Walnut Creek, CA 94596 Attention: Mr. Robert Thomas Chief, Materials Radiation Protection, Inspection, and Licensing Branch Section
Reference:
U.S. NRC License No. SNM-1405
Dear Mr. Thomas:
l IRT Corporation, with the assistance of G.A. Technologies, Inc., has completed the release surveys and decont. nination of several cells at the IRT LINAC located on property leased from G.A. Technologies, on their site at 10955 John Jay Hopkins Drive, San Diego, C4 92121. These cells have been decontaminated and are well within the NRC "GL delines for the Release of Facilities for t
Unrestricted Use".
The initial survey of the facility was completed by P.R. Maschka, the Radiation Safety Officer for IRT Corporation, in January,1984. The results these surveys are shown in Attachment A, " Release Surveys for the IRT LIN AC Located on the G.A. Technologies Site". These surveys showed that there was no removable contamination but that the walls had been activated and contained at i
least 600uCi of radioactive material.
This " Release" report was delivered to F.O. Bold of G.A. Technologies for his consideration. After several discussions between F.O. Bold and P.R. Maschka, it was decided to remove those parts of the LINAC walls that were most highly activated (Those areas are highlighted on Figures 2, 4, 5, 7, & 10 in Attachment A). Since the facility is to be returned to G.A. Technologies, Inc., it was decided that they would undertake the task of decontamination.
This work was completed on July 20, 1984. A meter and wipe survey was taken by R.J. Cockle, a G.A. Health Physics Surveyor, the results of his survey is shown in Attachment B, "IRT LINAC - End c4 Project Report. Release for Unrestricted Use".
The final meter survey (paragraph 5.0 of Attachment B) shows that the average reading in the LINAC cells had been reduced to less than 500 cpm as measured l
with a thin window G.M. pancake detector; the highest reading was 1000 epm on I
one block in the A Area wall and 800 epm on one brick in the CD Area wall. The final wipe surveys are shown in Figures 17,18, and 19. These wipes show that kere is no removable contamination.
Maibng Adoress P.O Box 85317. San Diego, CA 92138 I
8605060468 840925 PDR ADOCK 07001359 C
[(-
. Orporatiort U.S. NRC Region V August 13, 1984 Page Two IRT Corporation would like to have these rooms deleted from our License Nc.
SN M-1405.
G.A. Technologies, Inc. would like to take possession of these rooms for unrestricted use as soon as possible.
If you have any questions or need further information, please call me at (619) 450-4343, Ext. 449.
Sincerely, IRT CORPORATION etu.
de Paul R. Maschka Radiation Safety Officer l
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, Corporation : --
RELEASE SURVEYS FOR THE IRT LINAC LOCATED ON THE G.A. TECHNOLOGIES SITE All of the equipment was disassembled and removed from the Linac Cells A, B, and CD and each cell was cleaned. Complete meter and wipe surveys were taken of each cell. The meters used for the surveys were a Ludlum Geiger counter equipped with a pancake G.M. detector for Beta and Gamma, and an Eberline PAC-13A for Alpha. Some of the wipe samples were counted at the G.A.
Health Physics Laboratory and the rest were counted at the IRT Health Physics Laboratory.
NO REMOVABLE CONTAMINATION WAS FOUND ON ANY OF THE AREAS.
DIRECT ALPHA SURVEYS TAKEN WITH THE PAC-ISA WERE ALL BACKGROUND (LESS THAN 50 cpm).
The results of the surveys taken in September and November,1983 are shown on Figures 1 thru 13. Detailed brick by brick meter surveys taken in January,1984 are shown on Figures 14,15, and 16.
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OrporatiOrt INDUCED ACTIVITY ON THE WALLS OF THE IRT LINAC The walls of the facility contain concrete, steel, aluminum and lead.
The reactions that created the radioactive isotopes start with the high-energy electrons which are stopped in a high-density target creating Bremsstrahlung radiation. This bremsstrahlung, or gamma ray, is the actual instigator of the nuclear reaction. These gamma reactions can take many forms such as (gamma-n),
(gamma-2n), (gamma-np), (gamma-p), and (gamma-spalation); in addition there is the normal neutron capture reaction. These reactions are by no means all that can occur, but they are the more common. (1,2)
In order to determine the identity of the radioisotopes and the amount of activity, a GeLi detector and a Canberra Series 35 Multichannel analyzer were used to perform a gamma scan of the walls. The GeLi detector was surrounded by four inches of lead except for the front which faced the wall. The detector and lead " shield /collimator" was positioned in such a way that an 8-ft. x 8-ft.
section of wall was scanned. The areas that were scanned are the " hot spots" shown on Figures 2, 4, 5, 7, 8, and 10.
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. Corporation - --
The radionuclides that were identified in the walls are:
22 Na - 2.6 y 54 Mn - 313 d 57 Co - 271 d 60 Co - 5.27 y 40 plus the naturally occuring K. (3,4)
These are some of the same isotopes that have been identified at other accelerator facilities. (1,2)
The counting system was calibrated using sources that were spread out over an 8-ft. x 8-ft. area in a low background area in the LINAC Data Room.
With this calibration data the amount of each radionuclide induced in the LINAC walls could be calculated. The following table shows the calculated activity in the " hot spots" of the LINAC walls.
"A" AREA "B" AREA "B" AREA WEST WALL EAST WALL WEST WALL g________
g ___________
g __ _-- --
i Co -
3.4uCi Co -
0.19uCi Co - 0.04uCi 22 54 54 Na - 177.4uCi 2-4.4uCi Mn - 0.3 uCi 60 Co - 35.2uCi Co - 3.6 uCI 22 22 Na -
2.8uCi Na - 2.1 uCi i
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. Corporation TOTAL AREA "CD" AREA ACTIVITY EAST WALL WEST WALL ALL FIVE WALLS 57 II~
57
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Co -
0.25uCi Co -
0.9uCi Co -
1.4 uCi 54 54 54 i
2-5.4uCL 2-1.7uCI Mn -
11.8 uCi 60 60 60 Co - 48.6uCi Co 22 22, -
284 uCi Co 374.8 uCi 22 Na - 14.6uCi Na _
17.2uCl Na _ 214.1 uCi i
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1 IRT
.Cerporation'-
REFERENCES 1.
William P. Swanson, " Radiological Safety Aspects of the Operation of Electron Linear Accelerators" Chapter 2.6; Printed by the IAEA, February 1979.
2.
H. Wade Patterson and Ralph H. Thomas, " Accelerator Health Physics" Chapter 7; Academic Press,1973.
3.
M.A. Wakat, " Catalogue of Gamma Rays Emitted by Radionuclides," Nuclear Data Tables, Academic Press,1971.
4.
" Radiological Health Handbook" Revised Edition January 1970, U.S. Department of Health, Education, and Welfare, pp.110-113 and Section IV.
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ATTACHMENT A RELEASE SURVEYS FOR THE IRT LINAC IOCATED ON THE G.A. TECHNOLOGIES SITE s
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RELEASE SURVEYS FOR THE IRT LINAC LOCATED ON THE G.A. TECHNOLOGIES SI'lE All of the equipment was disassembled and removed from the Linac Cells A, B, and CD and each cell was cleaned. Complete meter and wipe surveys were taken of each cell. The meters used for the surveys were a thin window pancake G.M. detector for Beta and Gamma, and an Eberline PAC-ISA for Alpha. Some of the wipe samples were counted at the G.A. Health Physics Laboratory and the rest were counted at the IRT Health Physics Laboratory.
NO REMOVABLE CONTAMINATION WAS FOUND ON ANY OF THE AREAS.
DIRECT ALPHA SURVEYS TAKEN WITH THE PAC-1SA WERE ALL BACKGROUND (LESS THAN 50 cpm).
The results of the surveys taken in September and November,1983 are shown on Figures 1 thru 13. Detailed brick by brick meter surveys taken in January,1984 are shown on Figures 14,15,and 16.
INDUCED ACTIVITY ON THE WALLS OF THE IRT LINAC The walls of the facility contain concrete, steel, aluminum and lead.
The reactions that created the radioactive isotopes start with the high-energy electrons v!hich are stopped in a high-density target creating Bremsstrahlung radiation. This bremsstrahlung, or gamma ray, is the actual instigator of the nuclear reaction. These gamma reactions can take many forms such as (gamma-n),
(gamma-2n), (gamma-np), (gamma-p),and (gamma-spalation); in addition there is the normal neutron capture reaction. These reactions are by no means all that can occur, but they are the more common.(1,2)
In order to determine the identity of the radioisotopes and the amount of activity, a GeLi detector and a Canberra Series 35 Multichannel anlyze.r were used to perform a gamma scan of the walls. The GeLi detector was surrounded by four inches of lead except for the front which faced the wall. The detector
and lead " shield /collimator" was positioned in such a way that an 8-ft. x 8-ft.
section of wall was scanned. The areas that were scanned are the " hot spots" shown on Figures 2,4,5,7,8, and 10.
The radionuclides that were identified in the walls are:
22 Na - 2.6 y 54 Mn - 313 d 57 Co - 271 d 60 Co - 5.27 y 40 plus the naturally occuring K.(3,4)
These are some of the same isotopes that have been idintified at other accelerator facilities. (1,2)
The counting system was calibrated using sources that were spread out over an 8-ft. x 8-ft. area in a low background area in the LINAC Data Room.
With this calibration data the amount of each radionuclide induced in the LINAC walls could be calculated. The following table shows the calculated activity in the " hot spots" of the LINAC walls.
"A" AREA "B" AREA "B" AREA WEST WALL EAST WALL WEST WALL Co -
3.4uCi Co - 0.19uCi Co - 0.04uCi 22 54 54 Na - 177.4uCi
- Mn - 4.4uCi Mn - 0.3 uCi 60 60 Co - 35.2uCi Co - 3.6 uCi 22 22 Na - 2.8uCi Na - 2.1 uCi TOTAL "CD" AREA "CD" AREA ACTIVITY EAST WALL WEST WALL ALL, FIVE WALLS 57 57 57 Co - 0.25uCi Co -
0.9uCi Co -
1.4 uCi 54 54 54 Mn - 5.4uCi Mn -
1.7uCi Mn - 11.8 uCi 60 60 60 Co - 48.6uCi Co 22 22
- 284 uCi Co 374.8 uCi
~
22 Na - 14.6uCi Na _ 17.2uCi Na _ 214.1 uCi
.m,
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.-e REFERENCES 1.
William P. Swanson, " Radiological Safety Aspects of the Operation of Electron Linear Accelerators" Chapter 2.6; Printed by the IAEA, February 1979.
2.
H. Wade Patterson and Ralph H. Thomas, " Accelerator Health Physics" Chapter 7; Academic Press,1973.
3.
M.A.Wakat, " Catalogue of Gamma Rays Emitted by Radionuclides," Nuclear Data Tables, Academic Press,1971.
4.
" Radiological Health Handbook" Revised Edition January 1970, U.S. Department of Health, Education, and Welfare, pp.110-113 and Section IV.
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h 150 wall 150 100 100 well 100 Wall 100 100 100 100 100 Wall 100 LOO Mall A - ^88^
100 FI4OR ALL NUMBERS ARE 100
" " " "I " ICP"I Background = 100 cpm 100 "P"* # I' I"3 100 100 Wall 100 100 100 Wall 100 100 Wall 100 100 100 Wall 150 150 150 100 150 Wall 100 well 16.000 Wall too watt 100 sail aErea v
Figure 1. Linac "A" Area - Wall and Floor Direct Beta-Gamma Survey
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A - AABA BAST 1AALL stacked 100 100 100 s,f f, fffff,er concrete s
150 seas pipe slot 1000 1000 2 blocks 100 l
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[ go,i g,gg g, 400 16,000
)
' 1000 5
g00 150
""""I 600 400 200 100 150 All numbers are counta per minute (eps)
Background = 100 cpm September 7, 1983 Figure 2. Linac "n" Area East Wall toward "B" Area Direct Beta-Gamma Survey l
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100 Wall 100 Wall 100 l 1
Flight 100 Path 100 100 kI 100 100 100 All n ebers are counta 100 per minute (cym) 100 h ekgrount = 00 cp FLOOR iso, ember 14, 1983 100 100 100 100 100 100 100 TEms door 100 100 sail to II'll t' c-o Atsa 100 100 Wall 100wa1{00 100 Wall Entrance I"
100 door I
Figure 3. Linac "B" Area Floor Direct Beta-Gamma Survey
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n - AmeA rAst mu.
100 100 100 100
)\\8**m\\P1P4\\\\\\ \\k\\Ri/
100
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7 sonetrations -
Rall Fipe 100 180 100 lj E]E 200 to
/
ada tode 100 c-o systrist/ s si sr / >Q area A
'100 100 100 100 100 100 100 All numbers are counts per minute (cpm).
Background = 100 cpm movember 14, 1983 Figure 4. Linac "B" Area East Wall toward CD Area Direct Beta-Gamma Survey
- Anna wasr mu.
100 100 100 MSean Ploe Slot ////
Ball 5
100 2 ar/hr 0
"O 12,000 000 0 00 AM ///////
100 100 llo 100 100 th sh All nebers are counts per minute (cpm)
Background = 100 cpm November 14, 1983 Figure 5. Linac "B" Area West Wall toward A Area Direct Beta-Gamma Survey
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mall "See 390 3 Area 300 4
200 250 Collamae >r shield 200 300 200 All number are counts per minute (cym).
C-D AAEA FIDOR sackground = 200 cpm September 6, 1983 200 240 N
Beam Pipe N
200 250 200 Tunnel Entrance Figure 6. Linac TD" Area Floor Direct Beta-Gamma Lvey
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C-D AREA METF MALL 400 h \\ \\\\R\\\\ \\\\ \\\\\\\\\\\\\\\\ \\\\ \\X\\TV' 400
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600 60GN k
1000 Beam Mye slot Ball 400 e
1000 12b4 k m
'/
les s z arfar mm B Area 400 f
s S tora le f
400 4 caves S
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400 440 400 3 7777771 rr171777 77 7 rrr i s
All numbers are counts per minute (cpa)
Background = 400 cpm September 6, 1983 Figure 7. Linac "CD" Area West Wall toward B Area Direct Beta-Gamma Survey C-D AK:A BIORTE MALL Collimator ) 50
[00 2E 150 Shield 150
%,a 200 200 150 Tunnel 350Q350 p,
150 Hall itorage 350 400) 200
/
200 All numbers are counts per minute (cpa)
Background = 150 September 6, 1983 Figure 8. Linac "CD" Area North Wall Direct Beta-Gamma Survey s-4 m
1 i
C-D ARIA SAST MALL m mu m m,
2 1000 Q
200 1
150
/
300 1000
'f 10 team pipe slot j
200 200 200 pester Flight N 300 j
l 200 l
Path Pipe
/
0
- 1200 800 I /
238 s
ers t s i sii s sia 100 150 leorth 150 200 Ag, h *1 vent y1 100 All numeets are counts per minute (cpa)
Background = 100 cp September 8, 1983 Figure 9. Linac "CD" Area East Wall Direct Beta-Gamma Survey C-D AREA SOUTE NALL 100 250 15 0 200 400 200 250 t00 250 250 250 Hall 200 to 8 Area 100 200 250 250 All numbers are counts per minute (cpa)
Background = 100 cpr September 8, 1903 Figure 10. Linac "CD" Area South Wall Direct Beta-Gamma Survey 1
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Wipe Beta Alph No dge dpm 7
9 21 1
< 30
<5 Wall 2
4 30
<5 3
< 30
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<30
<5 5
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< 30
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< 30
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<5 Wipes were 1 square foot.
...it. re opm/100cmgrt.da.
28 y, g Wall 18 Wipes counted at IRT B.P. Lab. Oct. 21, 1983 g
17 2
24 Wall Wall Wall Wall 1
g4 27 16 26 15 25 sell to 8 Ared i
Figure 11. "A" Area Wipe Survey y
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Wipes were 1 ognare Smet.
Esculta reported as ope /100ca2 Wipes oeunted at IEF E.P. Lat.
Ostater 21, 1903 I
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to 19 mall le C-0 Asse A Aree 20 25 1
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499r ENTRANCE 8...
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el W2 wi e se ta Alpha P
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< 0. 01 4 1.94 we w9 Wall w1 Pes wre 1 square foot.
2 wall assults reported as dom /100cm 11 wipes counted at G.A. Technolow!
13 5.P. he September 6. 1983 and September 8, 1983.
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0 ATTAClefENT B IRT LINAC - END OF PROJECT REPORT RELEASE FOR UNRESTRICTED USE 1
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IN REPLY FROM R. J. Cockle REFER TO ra L. R. Quintana DATE July 23,1984 susJECT IRT Linac - End of Project Report Release for Unrestricted Use 1.0 PROJECT Clean up of Linec cells A, B, C-D located at Building 30.
The work was performed by Callahan Brothers Company under supervision and license of GA Technologies.
2.0 The main objective was to reduce to ALARA the radioactively activated cement block from walls separating A, B, and C-D rooms and to meet State and Federal requirements for decommissioning a facility to unrestricted use.
(a) Remove cement block to achievable (ALARA) levels.
(b) Monitor alI phases of operation.
(c) Preventing airborne contamination.
(d) Providing personnel monitor devices.
~
(e) Preventing Internal exposures.
l (f) Providing radiation monitoring equipment and l
protective clothing.
(g) Performing surveys, i.e., wipes on equipment wipes of cement blocks, lead bricks, wipes and exposure readings of packaged materials.
(h) Maintain adequate air sampling before and during the cleanup operation.
(I) Providing gamma scan of cement samples, l
3.0 Linac colI cleanup and subsequent packaging of the material was conducted during the period July 16-20, 1984.
4.0 Samples of the material were collected 9/83, and on 9/18/83 a scan CoS7, Mnusing thp4, and Na22, Ge(LI) detector (L122) showed positive amounts of Co 0, 6
5.0 Radiation survey results before and af ter cleanup of celi areas to ALARA levels.
(a) Release survey data for the IRT Linac located on the GA l
Technologies site, September,1983, as compared to data obtained after Julv 20. 10M.
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,7, Maximum Fwnesure Rate - GMfene)
Location Beta & Gamma (Measured at 1/2" from Surf ace)
Sept.1983 (BEFORE)
July 1984 (AFTC_R)
A Area E. Wati 16,000 cpm 800 cpm 2 mR/hr Except I block 1000 cpm B Area E. WalI 7000 cpm 300 cpm B Area W. Wali 12,000 cpm 200 cpm 2 mR/hr CD Area W. Wall 12,300 cpm 600 cpm 2 mR/hr CD Area N. WalI 400 cpm 300 cpm CD Area E. Wall 1200 cpm 1 brick 800 cpm -
others <500 cpm CD Area S. Wati 400 cpm 300 cpm 6.0 Eight (8) barrels and two (2) boxes of solidified waste have been filled for disposal through NMPC to a licensed burial site.
.The maximum reading is 12 mR/hr on the surface of a reading box and <0.5 mR/hr at 1 meter on the same box.
7.0 Air samnline Procram Special air sampiIng was conducted in the A, B, CD areas during cleanup.
No air sample detected any activity 2.1% of MPC for the isotopes observed by gamma scan.
8.0 Personnel MonItorino - Fiim Dosimeter Results (a)
Callahan Brothers Company employees are not expected to receive a dose exceeding the minimum detectable level for beta-gamma film dosimeters which is <10 mrom gamma for the period July 16 through 20.
9.0 Wfom samnies Areas A, B, C & D were wipe checked July,1984 Reference Log Book No. 87SS pages 108 and 113. See Figures 17, 18, and 19.
No results exceeded 10 dpm beta /100 cm2 area 5 dpm alpha /100 cm2 area 10.0 BIcassav Measurements "In Vivo" Whole Body Counting No in-vivo total body counts required due to:
(a)
No positive wipe results - no significant contamin'ation.
(b) All air samples <1% MPC (c) All personnel were monitored at close of each workday.
No detectable contamination to person or to work clothes.
AlI counts background by cpm counter (<150 cpm).
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Wipe Be to Alph No d
dpm 6 WALL 1
i <4 42 4
5 2
0.8
<2 3
40.8
<2
< 0. 8
<2 7 WALL
^LL 1.0
<2 3
6 1.8 42 7
1.0
<2 8
40.8 42 2
Wipes were 1 square foot.
Results ce rted as dpm/100 cm 1
Wipes counted at G. A.
H.P. Lab. 7/20/84 Hall to B Ared l
FIGURE 17.
"A" Area Wipe Survey j
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._..___9 Flight Path Beam Pg 7
6 8
i t
10 WALL Wipe Beta Alpha No.
dpm dpm 1
40.8 42 2
1.0
<2 3
1.5
<2 4
40.8
<2 5
< 0. 8
<2 B-AREA 6
<0.8
<2 FLOOR 7
<0.8
<2 8
40.8 42 9
< 0. 8 42
~
10
<0.8 42 11 1.0
<2 12
< 0. 8
<2 5
Wipes were 1 square foot.
Results reported as dpm/100 cm2,
- nleid door Wipes counted at G.A.
H.P.
Lab.
7/20/84 H311 to Hall to 4
A Area C-D Area I
11 WALL 12 WALL I'~~~~ 6 ft l
ENTRANCE door 8-----
2 FIGURE 18. LINAC "B" Area Wipe Survey
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M:UR SAFECUARDS k FCTC OTilER P ' E C f'I NIO:1:
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