ML092720604

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Room 128, Contained Both Wet and Dry Plutonium Process Glove-Boxes
ML092720604
Person / Time
Site: 07000925
Issue date: 11/02/1989
From: Rogers W
Cimarron Corp
To:
Region 3 Administrator
Shared Package
ML092720355 List:
References
Download: ML092720604 (19)
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Text

{{#Wiki_filter:ROOM 128 Room 128 contained both wet and dry plutonium process glove-boxes. During production there had not only been a number of spills from these boxes but there was also a small fire in this room involv-ing a small amount of nuclear material. After this fire the walls, floor, ceiling and all equipment in this room were painted. After glovebox removal, this entire room was vacu-blasted and the floor coating was removed. We found approximately 2000 to 3000 2 dpm/100 cm direct on isolated spots on the floor and ceiling sup-port beam. Approximately 25% of the floor had reading of approx-imately 500 dpm/100 cm2 direct and four spots on the walls also 2 had approximately 500 dpm/100 cm direct. A liquid process line that passed through the north block wall of this room had leaked down inside these blocks. The north wall was removed and the entire floor and hot spots on the other walls were reblasted. A number of pipe sleeves that were installed in room 128 floor had to be removed because of high gamma readings. We used a Ludlum 2220 with a Ludlum 43-17 low energy gamma probe to identify all cracks and seams that might need decontami-nation. A Ludlum 2220 with a Ludlum 43-68, 43-4, or 43-27 was used with P-10 gas for all alpha release surveys. All smears were taken on Whatman smear paper and counted in a Hewwlett-Packard 5560 A (low background) automatic sample counter. W. A. Rogers ROOM' 128 Room 128 contained both wet and dry plutonium process glove-boxes. During production there had not only been a number of spills from these boxes but there was als'b a small fire in this room involv-ing a small amount of nuclear material. After this fire the walls, floor, ceiling and all equipment in this room were painted. After glovebox removal, this' entire room was vacu-blasted and the floor coating was removed. We found approximately 2000 to 3000 dpm/IOO cm2 direct on isolated spots on the floor and ceiling sup-port beam. Approximately 25% of the floor had reading of approx-imately 500 dpm/IOO cm2 direct and four spots on the walls also had approximately 500 dpm/IOO cm2 direct. A liquid process line that passed through the north block wall of this room had leaked down inside these blocks. The north wall was removed and the entire floor and hot spots on the other walls were reblasted. A number of J pipe sleeves that were installed in room 128 floor had to be removed ,r. because of high gamma readings. We used a Ludlum 2220 with a Ludlum 43-17 low energy gamma probe to identify all cracks and seams that might need decontami-nation. A Ludlum 2220 with a Ludlum 43-68, 43-4, or 43-27 was used with P-lO gas for all alpha release surveys. All smears were taken on Whatman smear paper and counted in a Hewwlett-Packard 5560 A (low background) automatic sample counter *. '

    • -N~***a,.* *.~

W. A. Rogers"

Pu PLANT RELEASE SURVEY PLAN

1. For initial decontamination all surfaces will be scanned with an Eberline PRM-6 with a Radeco alpha scintillation probe.

Back-ground will be maintained at less than 100 CPM(200 dpm). All areas greater than twice background will be marked and reading will be taken with a release survey instrument to document cont-amination levels and random large area smears will be taken.

2. After these initial areas are decontaminated, all floor surfaces and the base of each wall will be completely surveyed with a digital readout release instrument and a Ludlum large area gas proportional alpha detector and random smear samples will be taken.

Release instrumentation shall have a minimum detectable level of at least 50 dpm/100 cm2.

3.

All hot spots greater than or equal to 100 dpm/100 cm2 ident-ified will be decontaminated.

4. A random survey with a release instrument will be taken on the walls and ceiling to try to identify any other problem areas.
5.

If no problems are identified, each room will be gridded off into approximately 2 meter on a side square on the walls and floor and five readings will be taken in each grid. Readings shall be taken in the center and at the midpoint from the center to each corner.

6.

Each ceiling has closely spaced rafters that will not be easily divided into 2 meter squares. Because of this, we will take readings on the bottom of each rafter at 2 meter inter-vals and one reading centered on the ceiling between rafters. Readings on each rafter will be staggered one meter.

7. These release readings will be documented on a map that is drawn to approximately scale measurements in meters.
8.

Data provided on each map:

1. Survey block numbers, identifiable on a scale drawings.
a. room or area name or number.
b. surface surveyed.
c. type of measurement and units.
2.

Name of surveyor taking measurements, date of survey, and

  • location.

Pu PLANT'RELEASE SURVEY PLAN

1. For initial decontamination all surfaces will be scanned with an Eberline PRM-6 with a Radeco alpha scintillation probe.

Back-ground will be maintained at less than 100 CPM(200 dpm). All areas greater than twice background will be marked and reading will be taken with a release survey instrument to document cont-amination levels and random large area smears will be taken.

2. After these initial areas are decontaminated, all floor surfaces and the base of each wall will be completely surveyed with a digital readout release instrument and a Ludlum large area gas proportional alpha detector and random smear samples will be taken.

Release instrumentation shall have a minimum detectable level of at least 50 dpm/IOO cm2 *

3. All hot spots greater than or equal to 100 dpm/IOO cm2 ident-ified will be decontaminated.
4. A random survey with a release instrument will be taken on the walls and ceiling to try to identify any other problem areas.
5. If no problems are identified, each room will be gridded off into approximately 2 meter on a side square on the walls and floor and five readings will be taken in each grid.

Readings shall be taken in the center and at the midpoint from the center to each corner.

6. Each ceiling has closely spaced rafters that will not be easily divided into 2 meter squares.

Because of this, we will take readings on the bottom of each rafter at 2 meter inter-vals and one reading centered on the ceiling' between rafters. Readings on each rafter will be staggered one meter.

7. These release readings will be documented on a map that is drawn to approximately scale measurements in meters.
8. Data provided on each map:
1.

Survey block numbers, identifiable on a scale drawings~

a. room or area name or number.
b. surface surveyed.
c. type of measurement and units.
2.
  • Name of surveyor taking measurements, date of survey, and location.
3.

Type, model number, calibration data, sensitivity limit, background, and source response of instruments used in survey.

4.

When a block surveyed is below the sensitivity of the instru-ment, the fact that such a measurement was made should be included as significant data.

9. All release survey smears will be taken on Whatman smear paper and counted in the automatic sample counters.

Each smear will cover approximately 100 cm2.

10. There will be at least 30 survey blocks in each area to be released.
11. Piping and ductwork will be surveyed on all accessable sides at 2 meter intervals.

If more than one line is running parallel in a pipe rack, readings shall be staggered at one meter intervals.

12. All readings taken that only cover part of a probe area will be corrected to dpm/100 cm2.
13.

No survey block will measure less than one meter on a side.

14.

No survey block will measure more than 3 meters on a side.

15. All portable release survey instruments will be calibrated quarterly and all instruments in use will be source checked daily.
3.

Type, model number, calibratiori data, sensitivity limit, background, and source response of instruments used in survey.

4.

When a block surveyed is below the sensitivity of the instru-ment, the fact that such a measurement was made should be included as significant data.

9. All release survey smears will be taken on Whatman smear paper and counted in the automatic sample counters.

Each smear will cover approximately 100 cm2 *

10. There will be at least 30 survey blocks in each area to be released.
11. Piping and ductwork will be surveyed on all accessable sides at 2 meter intervals.

If more than one line is running parallel in a pipe rack, readings shall be staggered at one meter intervals.

12. All readings taken that only cover part of a probe area will be corrected to dpm/IOO cm2 *
13. No survey block will measure less than one meter on a side.
14. No survey block will measure more than 3 meters on a side.
15. All portable release survey instruments will be calibrated quarterly and all instruments in use will be source checked daily.

Table 1-1. Acceptable surface contamination levels Nuclides ( Averageb'C'J MaximumlblId Removahleb,e.f U-nat, U-235, U-238, and 5,000 dpm a/100 cm2 15,006 dpm u/lWO cm 2 1,000 dl)m u/i0 cm2 associated decay products Transuranics, Ra-226, Ra-228, 100 dpm/l0W cm2 300 dpm/IUU cm 2 20 dprm/I00 cm2 Th-230, Th-228, Pa-231, Ac-227, 1-125, 1-129 Tb-nat, Th-232, Sr-90 1,000 dpm/l0( cm 2 3,000 dpm/IOU cm2 200 dpm/100 cm2 Ra-223, Ra-224, U-232, 1-126, 1-131, 1-133 Beta-gamma emitters (nuclides 5,000 dpm By/I00 cm2 15,000 dpm By/100 cm' 1,000 dpm By/g00 cm2 with decay modes other than alpha emission or spontaneous fission) except Sr-90 and other noted above. aWhere surface contamination by both alpha-and beta-Ramma-emitting nuclides exists, the limits established for alpha-and beta-gamma-emitting nuclides should apply independently. bAs used in this table, dpm (disintegrations per minute) means the rate of emission by radinaictive material as determined by correcting the counts per minute observed by an appropriate detector for background, efficiency, and geometric factors associated with the instrumentation. CHeasurements of average contaminant should not he averaged over more than I square meter. For objects of less surface area, the average should be derived for each such object. dThe maximum contamination level applies to an area of not more than 100 cm2. eThe amount of removable radioactive material per 100 cm2 of surface area should be determined by wiping that area with dry filter or soft absorbent paper, applying moderate pressure, and assessing the amount of radioactive material on the wipe with an appropriate instrument of known efficiency. When removable contamination on objects of less surface area is determined, the pertinent levels should be reduced proportionally and the entire surface should be wiped. fThe average and maximum radiation levels associated with surface contamination resulting from beta-gamma emitters should not exceed 0.2 mrad/hr at 1 cm and 1.0 mrad/hr at 1 cm, respectively, measured through not more than 7 milligrams per square centimeter of total absorber. Table 1-1. Nuclides,l Acceptable surface contamination levels b,~ J' Average,., b.] J' MaXImum ', b J' llemov:1hle,e, U-nat, U-235, U-238, and associated decay products 5,000 dpm a/lOO cm 2 15,006 lipm u/1UO cm 2 1,000 dpm u/IOO cm 2 Transuranics, Ra-226, Ra-228, Th-230, Th-228, Pa-23I, Ac-227, 1-125, 1-129 TIl-nat, Th-232, Sr-90 Ra-223, Ra-224, U-232, 1~126, 1-131, 1-133 Beta-gamma emitters (nuclides with decay modes other than alpha emission or spontaneous fission) except Sr-90 and other noted above. 100 dpm/IOO cm 2 1,000 dpm/lOO cm 2 5,000 dpm By/IOO cm 2 300 dpm/IUU cm 2 20 dl'0I/lOO cm 2 3,0.00 dpm/IOO cm 2 200 dpm/ 1U0 cm 2 15,000 dpm By/IOO em' 1,000 dpm By/IOO cm 2 aWhere surface contamination by both alpha-nnd hE'ta-gamma-emitting nuclides ('xi~t!:, the limit!: establish('d for all'ha-and beta-gamma-emitting nuclides should apply independently. bAs used in thi~ table, dpm (disintE'gration~ per minute) me.. n~ the rate of emi~~ion hy r""in~('tive material ns detl'rmined by conecting the counts per minute observed by an appropriate detector for background. efficiency, allu geometric factors associated with the instrumentation. cMeasurements of average contaminant should not he avcra~cd over more than I square meter. I:or objects of less'surface area, the average should be derived for each such object. ~he maximum contamination level applie~ to an area of not more than 100 cm 2

  • eThe amount of removable radioactive matE'rial per 100 cm l of surface area ~hould hI.' determined hy wIping that area with dry filter or soft absorbent paper, applying moderate pressure, and assessing the amount of rauioactive material on the wipe with an appropriate instrument of known efficiency.

When removahle contamination on object~ of less surface area is determined, the pertinent levels should be reduced proportionally and the entire surface should be wiped. 'The average and maximum radiation levels associated with surface contamination resultin~' from heta-gamma emitters should not exceed 0.2 mrad/hr at 1 em and 1.0 mrad/hr at 1 cm, respectively, measured through not more than 7 milligrams per square centimeter of total ahsorber.

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